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Sample records for sacramento rancho seco-2 reactor

  1. An economic evaluation of the economics of the Rancho Seco nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Craig, P P [California Univ., Davis, CA (USA). Dept. of Applied Science; Marcus, W B [JBS Energy, Inc., Broderick, CA (USA)

    1991-03-01

    Escalating costs of operating reactors may make it economically advantageous to close them down and purchase small, cheap technologies such as combined-cycle systems. We examine the arguments pro and con for the Rancho Seco nuclear reactor, owned by the Sacramento Municipal Utility District (SMUD) and now permanently shut-down. We conclude that if the reactor could be run no better than it has run in the past, there was no clear advantage to continued operation. Optimistic scenarios show a net advantage to running it, and pessimistic scenarios show a net disadvantage. The total range of plausible costs is narrow; the financial impact of either choice on consumers would have been small. The analysis suggests that decisions on whether to close down existing reactors are highly case specific, but that strong economic arguments for shut-down can exist if reactor performance is poor and/or if maintenance expenses are high. (author).

  2. An economic evaluation of the economics of the Rancho Seco nuclear reactor

    International Nuclear Information System (INIS)

    Craig, P.P.

    1991-01-01

    Escalating costs of operating reactors may make it economically advantageous to close them down and purchase small, cheap technologies such as combined-cycle systems. We examine the arguments pro and con for the Rancho Seco nuclear reactor, owned by the Sacramento Municipal Utility District (SMUD) and now permanently shut-down. We conclude that if the reactor could be run no better than it has run in the past, there was no clear advantage to continued operation. Optimistic scenarios show a net advantage to running it, and pessimistic scenarios show a net disadvantage. The total range of plausible costs is narrow; the financial impact of either choice on consumers would have been small. The analysis suggests that decisions on whether to close down existing reactors are highly case specific, but that strong economic arguments for shut-down can exist if reactor performance is poor and/or if maintenance expenses are high. (author)

  3. Safety Evaluation Report related to the restart of Rancho Seco Nuclear Generating Station, Unit 1, following the event of December 26, 1985 (Docket No. 50-312)

    International Nuclear Information System (INIS)

    1987-10-01

    On December 26, 1985, the Rancho Seco Nuclear Generating Station, owned and operated by the Sacramento Municipal Utility District (SMUD), experienced a loss of dc power within the integrated control system (ICS) while the plant was at 76% power. The ensuing reactor trip was followed by a rapid overcooling transient and automatic initiation of the safety features actuation system (SFAS). The overcooling transient continued until ICS dc power was restored 26 minutes after its loss. Two letters from the NRC Region V Administrator (dated December 26, 1985) confirmed that the Rancho Seco plant would not be returned to power operation until SMUD (the licensee) had provided the NRC with an assessment of the root cause of the transient and a justification as to why the Rancho Seco facility is ready to resume power operation. In response, the licensee submitted the ''Rancho Seco Action Plan for Performance Improvement'' on July 3, 1986; revisions to that action plan were submitted on December 15, 1986 and February 28, 1987. The NRC staff has reviewed the action plan and numerous other supporting documents submitted by the licensee. The staff's evaluation of the information supporting restart of Rancho Seco is presented in this safety evaluation report

  4. Dose to man from a hypothetical loss-of-coolant accident at the Rancho Seco Nuclear Power Plant

    International Nuclear Information System (INIS)

    Peterson, K.R.; Greenly, G.D.

    1981-02-01

    At the request of the Sacramento Municipal Utilities District, we used our computer codes, MATHEW and ADPIC, to assess the environmental impact of a loss-of-coolant accident at the Rancho Seco Nuclear Power Plant, about 40 kilometres southeast of Sacramento, California. Meteorological input was selected so that the effluent released by the accident would be transported over the Sacramento metropolitan area. With the release rates provided by the Sacramento Municipal Utilities District, we calculated the largest total dose for a 24-hour release as 70 rem about one kilometre northwest of the reactor. The largest total dose in the Sacramento metropolitan area is 780 millirem. Both doses are from iodine-131, via the forage-cow-milk pathway to an infant's thyroid. The largest dose near the nuclear plant can be minimized by replacing contaminated milk and by giving the cows dry feed. To our knowledge, there are no milk cows within the Sacramento metropolitan area

  5. Rancho Seco--Decommissioning Update

    International Nuclear Information System (INIS)

    Newey, J. M.; Ronningen, E. T.; Snyder, M. W.

    2003-01-01

    The Rancho Seco Nuclear Generating Station ceased operation in June of 1989 and entered an extended period of SAFSTOR to allow funds to accumulate for dismantlement. Incremental dismantlement was begun in 1997 of steam systems and based on the successful completion of work, the Sacramento Municipal Utility District (SMUD) board of directors approved full decommissioning in July 1999. A schedule has been developed for completion of decommissioning by 2008, allowing decommissioning funds to accumulate until they are needed. Systems removal began in the Auxiliary Building in October of 1999 and in the Reactor Building in January of 2000. Systems dismantlement continues in the Reactor Building and should be completed by the end of 2003. System removal is near completion in the Auxiliary Building with removal of the final liquid waste tanks in progress. The spent fuel has been moved to dry storage in an onsite ISFSI, with completion on August 21, 2002. The spent fuel racks are currently being removed from the pool, packaged and shipped, and then the pool will be cleaned. Also in the last year the reactor coolant pumps and primary piping were removed and shipped. Characterization and planning work for the reactor vessel and internals is also in progress with various cut-up and/or disposal options being evaluated. In the year ahead the remaining systems in the Reactor Building will be removed, packaged and sent for disposal, including the pressurizer. Work will be started on embedded and underground piping and the large outdoor tanks. Building survey and decontamination will begin. RFP's for removal of the vessel and internals and the steam generators are planned to fix the cost of those components. If the costs are consistent with current estimates the work will go forward. If they are not, hardened SAFSTOR/entombment may be considered

  6. Loss of integrated control system power and overcooling transient at Rancho Seco on December 26, 1985

    International Nuclear Information System (INIS)

    1986-02-01

    On December 26, 1985, Rancho Seco Nuclear Generating Station, located in Clay, California, about 25 miles southeast of Sacramento, experienced a loss of dc power within the integrated control system (ICS) while the plant was operating at 76% power. The plant is owned by the Sacramento Municipal Utility District (SMUD). Following the loss of ICS dc power, the reactor tripped on high reactor coolant system (RCS) pressure followed by a rapid overcooling transient and automatic initiation of the safety features actuation system on low RCS pressure. The overcooling transient continued until ICS dc power was restored 26 minutes after its loss. The fundamental causes for this transient were design weaknesses and vulnerabilities in the ICS and in the equipment controlled by that system. These weaknesses and vulnerabilities were not adequately compensated by other design features, plant procedures or operator training. These weaknesses and vulnerabilities were largely known to SMUD and the NRC staff by virtue of a number of precursor events and through related analyses and studies. Yet, adequate plant modifications were not made so that this event would be improbable, or so that its course or consequences would be altered significantly. The information was available and known which could have prevented this overcooling transient; but in the absence of adequate plant modifications, the incident should have been expected. The report includes findings and conclusions of the NRC Incident Investigation Team sent to Rancho Seco by the NRC Executive Director for Operations in conformance with NRC's recently established Incident Investigation Program. 33 figs

  7. Methodology and application of surrogate plant PRA analysis to the Rancho Seco Power Plant: Final report

    International Nuclear Information System (INIS)

    Gore, B.F.; Huenefeld, J.C.

    1987-07-01

    This report presents the development and the first application of generic probabilistic risk assessment (PRA) information for identifying systems and components important to public risk at nuclear power plants lacking plant-specific PRAs. A methodology is presented for using the results of PRAs for similar (surrogate) plants, along with plant-specific information about the plant of interest and the surrogate plants, to infer important failure modes for systems of the plant of interest. This methodology, and the rationale on which it is based, is presented in the context of its application to the Rancho Seco plant. The Rancho Seco plant has been analyzed using PRA information from two surrogate plants. This analysis has been used to guide development of considerable plant-specific information about Rancho Seco systems and components important to minimizing public risk, which is also presented herein

  8. Socio-economic impacts of nuclear generating stations: Rancho Seco case study

    International Nuclear Information System (INIS)

    Bergmann, P.A.

    1982-07-01

    This report documents a case study of the socio-economic impacts of the construction and operation of the Rancho Seco nuclear power station. It is part of a major post-licensing study of the socio-economic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period 1980 to 1981. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of the construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socio-economic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

  9. Environmental radiological studies conducted during 1986 in the vicinity of the Rancho Seco Nuclear Power Generating Station

    International Nuclear Information System (INIS)

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Brunk, J.L.; Jokela, T.A.

    1987-03-01

    This report summarizes the information compiled in 1986 for our assessment of the environmental impact of radionuclides discharged with aqueous releases from the Rancho Seco Nuclear Power Generating Plant. In October 1984, a liquid-effluent control program was initiated that significantly reduced the quantities of radionuclides discharged with liquid waste from the plant. However, results from our sampling program in 1986 indicate that previously discharged radionuclides persist in the downstream environment and are found in many aquatic dietary components although at concentrations much lower than those measured in 1984 and 1985. The greatly reduced activities in the dietary components from the aquatic environment attest to the effectiveness of the liquid-effluent control program. Concentrations in the flesh of fish from the creeks have decreased over time and with distance from the plant outfall. The mean concentration of 137 Cs in fish collected from Laguna Creek at locations more than 7.5 km from Rancho Seco is now comparable to the concentration determined in fresh-water fish randomly selected from Chicago, Illinois, markets. By August 1986, the mean concentration of 137 Cs in the flesh of bluegill had fallen to 7% of the concentration measured in fish from comparable locations in 1984 and was 30% of the mean concentration measured in these fish during August 1985. Stable potassium in the water plays a major role in the accumulation of 137 Cs by fish. Concentrations of 137 Cs in the surface sections of creek sediments also declined between the end of 1984 and 1986 with an effective half-life of approximately 2 y. Surface soils collected around a perimeter 11 km from Rancho Seco and from ranchlands closer to the plant showed only concentrations of 137 Cs originating from global fallout. Soils previously irrigated with Clay Creek water retain levels of both 134 Cs and 137 Cs

  10. Socioeconomic impacts of nuclear generating stations: Rancho Seco case study. Technical report 1 Oct 78-4 Jan 82

    International Nuclear Information System (INIS)

    Bergmann, P.A.

    1982-07-01

    The report documents a case study of the socioeconomic impacts of the construction and operation of the Rancho Seco nuclear power station. It is part of a major post-licensing study of the socioeconomic impacts at twelve nuclear power stations. The case study covers the period beginning with the announcement of plans to construct the reactor and ending in the period, 1980-81. The case study deals with changes in the economy, population, settlement patterns and housing, local government and public services, social structure, and public response in the study area during the construction/operation of the reactor. A regional modeling approach is used to trace the impact of construction/operation on the local economy, labor market, and housing market. Emphasis in the study is on the attribution of socioeconomic impacts to the reactor or other causal factors. As part of the study of local public response to the construction/operation of the reactor, the effects of the Three Mile Island accident are examined

  11. Rancho Seco building wake effects on atmospheric diffusion

    International Nuclear Information System (INIS)

    Start, G.E.; Cate, J.H.; Dickson, C.R.; Ricks, N.R.; Ackerman, G.R.; Sagendorf, J.F.

    1977-11-01

    A series of 23 paired gaseous tracer releases at the Rancho Seco Nuclear Power Station in 1975 was the third of several tests designed to investigate the diffusion characteristics of the atmosphere under conditions of low windspeed and temperature inversion. This test also evaluated the effects of flow around buildings upon dilution of pollutants. Gaseous tracers were laterally dispersed about six times more than the expected amounts from Pasquill--Gifford curves of sigma-y. Most of this increase could be related to observed variance of the horizontal wind direction (meandering). For ground-level releases the effective sigma-z values were 16 times greater than the corresponding values from the Pasquill--Gifford curves. Measured ground-level axial concentrations were about 75 times smaller than predicted by the Gaussian diffusion equation for a ground-level release when Pasquill--Gifford values of sigma-y and sigma-z were used

  12. Confirmatory Survey Results for the Reactor Building Dome Upper Structural Surfaces, Rancho Saco Nuclear Generating Station, Herald, California

    International Nuclear Information System (INIS)

    Wade C. Adams

    2006-01-01

    Results from a confirmatory survey of the upper structural surfaces of the Reactor Building Dome at the Rancho Seco Nuclear Generating Station (RSNGS) performed by the Oak Ridge Institute for Science and Education for the NRC. Also includes results of interlaboratory comparison analyses on several archived soil samples that would be provided by RSNGS personnel. The confirmatory surveys were performed on June 7 and 8, 2006

  13. Environmental radiological studies downstream from Rancho Seco Nuclear Power Generating Station

    International Nuclear Information System (INIS)

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Dawson, J.W.; Brunk, J.L.; Jokela, T.A.

    1985-01-01

    This report summarizes the information compiled in 1984 while assessing the environmental impact of radionuclides in aquatic releases from the Rancho Seco Nuclear Power Generating Station. Gamma-emitting radionuclides discharged since 1981 are found in many of the dietary components derived from the creeks receiving the effluent wastewater. Some soils and crops are found to contain radionuclides that originate from the contaminated water that was transferred to land during the irrigation season. 134 Cs and 137 Cs are the primary gamma-emitting radionuclides detected in the edible flesh of fish from the creeks. Concentrations in the flesh of fish decreased exponentially with distance from the plant. No significant differences in the 137 Cs activity were found between male and female fish of equal size, but concentrations may vary in fish of different size, with the season and diet. 21% of the total 137 Cs and 134 Cs discharged between 1981 and 1984 is associated with the creek sediments to a distance of 27 km from the plant. Fractions of the missing inventory have been transferred to land during the irrigation season or to downstream regions more distant than 27 km from the plant. The radiocesium content of the sediments in 1984 decreased significantly in a downstream direction, much in the same manner as concentrations decreased in fish. Radioactivity originating from the plant was not above detection limits in any terrestrial food item sampled beyond 6.5 km from the plant. Based on the usage factors provided by individuals interviewed in a 1984 survey, the fish and aquatic-organism ingestion pathway contributed the largest radiological dose to humans utilizing products contaminated with the radionuclides in the liquid wastes discharged from the Rancho Seco Nuclear Power Generating Station in 1984

  14. Aerial radiological survey of the creeks and tributaries near the Rancho Seco Nuclear Generation Station, Clay Station, California. Date of survey: December 1984

    International Nuclear Information System (INIS)

    1986-06-01

    Radiological contamination due to man-made radionuclides was detected using hand-held instruments in the summer of 1984 in the creeks and tributaries near the Rancho Seco Nuclear Generating Station at Clay Station, California. To help determine the extent of the contamination an aerial radiological survey centered over the creeks and tributaries and including the Rancho Seco facility was conducted during the period 3 to 15 December 1984. Radiological contaminants were detected along a 9-mile segment of the system of creeks in the area. These contaminants included cesium-134, cesium-137, and cobalt-60. Radiation measurements away from the contaminated areas were the same as those made during the aerial radiological survey conducted in 1980

  15. Rancho Seco liquid effluent pathway aquatic and terrestrial dietary survey report

    International Nuclear Information System (INIS)

    Eagle, R.J.; Wong, K.M.; Noshkin, V.E.

    1984-01-01

    This report is a detailed summary of a survey conducted to identify all environmental pathways that may lead to any potential radiological dose to individuals utilizing aquatic and terrestrial components possibly contaminated with radionuclides contained in the liquid effluents that have been routinely discharged since 1980 to Clay Creek from the Rancho Seco Nuclear Generating Station. All land users and identified residents who obtain food from the creeks or use the creek water for irrigation or recreation were interviewed. Site specific usage parameters for the consumption of different food products and for direct exposure to individuals at downstream locations were identified and are discussed in this report. These usage parameters will be used with appropriate radionuclide concentration data to estimate radiological dose to man from the identified liquid effluent pathways

  16. Aerial radiological survey of the Rancho Seco Nuclear Generating Station, Clay Station, California, 18 January 1980 to 1 February 1980

    International Nuclear Information System (INIS)

    1980-11-01

    An airborne radiological survey of 260 km 2 area centered over the Rancho Seco Nuclear Generating Station was made 18 January through 1 February 1980. Detected radioisotopes and their associated gamma ray exposure rates were consistent with that expected from normal background emitters, except directly over the station. Count rates observed at 90 m altitude were converted to exposure rates at 1 m above the ground and are presented in the form of an isopleth map

  17. Putting the sun to work in Sacramento

    International Nuclear Information System (INIS)

    Osborn, D.E.

    2000-01-01

    At dawn this morning, the sun went to work for customers of the Sacramento Municipal Utility District (SMUD). The largest photovoltaic (PV) power plant in the world, adjacent to the closed nuclear power plant at Rancho Seco, generated enough electricity for over a thousand customers, rooftop solar water heaters lowered thousands of residential electric bills and rooftop PV systems turned hundreds of Sacramento homes into mini power plants. SMUD, in partnership with their customers-owners, is leading the way in putting the sun to work today. SMUD plans to have at least half of its energy come from energy efficiency, existing hydroelectric plants and renewable resources in this decade. SMUD expects investments made in solar power today to provide its customer-owners with substantial long-term energy, environmental and community benefits. This article describes some of SMUD's efforts

  18. Technical evaluation of RETS-required reports for Rancho Seco Nuclear Generating Station, Unit 1 for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed for the Rancho Seco Nuclear Generating Station, Unit 1 were the Semiannual Effluent Release Report, January 1, 1983 to June 30, 1983 and the Radiation Exposure, Environmental Protection, Effluent and Waste Disposal Report. The principal review guidelines were the plant's specific RETS which were based on NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  19. Demonstration of a transportable storage system for spent nuclear fuel

    International Nuclear Information System (INIS)

    Shetler, J.R.; Miller, K.R.; Jones, R.E.

    1993-01-01

    The purpose of this paper is to discuss the joint demonstration project between the Sacramento Municipal Utility District (SMUD) and the US Department of Energy (DOE) regarding the use of a transportable storage system for the long-term storage and subsequent transport of spent nuclear fuel. SMUD's Rancho Seco nuclear generating station was shut down permanently in June 1989. After the shutdown, SMUD began planning the decommissioning process, including the disposition of the spent nuclear fuel. Concurrently, Congress had directed the Secretary of Energy to develop a plan for the use of dual-purpose casks. Licensing and demonstrating a dual-purpose cask, or transportable storage system, would be a step toward achieving Congress's goal of demonstrating a technology that can be used to minimize the handling of spent nuclear fuel from the time the fuel is permanently removed from the reactor through to its ultimate disposal at a DOE facility. For SMUD, using a transportable storage system at the Rancho Seco Independent Spent-Fuel Storage Installation supports the goal of abandoning Rancho Seco's spent-fuel pool as decommissioning proceeds

  20. Environmental radiological studies downstream from the Rancho Seco Nuclear Power Generating Station, 1985

    International Nuclear Information System (INIS)

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Brunk, J.L.; Jokela, T.A.

    1986-01-01

    Information compiled in 1985 while assessing the environmental impact of radionuclides previously discharged with aqueous releases from the Rancho Seco Nuclear Power Generating Plant is presented. In October 1984, the quantities of gamma-emitting radionuclides in water discharged to Clay Creek from the plant were reduced below operationally defined detection limits for liquid effluents. However, radionuclides previously discharged persist in the downstream environment and are found in many aquatic dietary components. 134 Cs and 137 Cs are the primary gamma-emitting radionuclides detected in the edible flesh of different fish, crayfish, and frogs. Coefficients for exponential equations are generated, from a least square analysis, that relate the change in concentration of 137 Cs in fish to distance downstream and time between March and October 1985. Concentrations of 137 Cs in surface creek sediments also decreased in the downstream direction much in the same manner as concentrations decreased in fish. However, there was no significant difference in the radiocesium concentrations in surface sediements collected from comparable locations during both 1984 and 1985

  1. Operating US power reactors

    International Nuclear Information System (INIS)

    Silver, E.G.

    1988-01-01

    This update, which appears regularly in each issue of Nuclear Safety, surveys the operations of those power reactors in the US which have been issued operating licenses. Table 1 shows the number of such reactors and their net capacities as of September 30, 1987, the end of the three-month period covered in this report. Table 2 lists the unit capacity and forced outage rate for each licensed reactor for each of the three months (July, August, and September 1987) covered in this report and the cumulative values of these parameters since the beginning of commercial operation. In addition to the tabular data, this article discusses other significant occurrences and developments that affected licensed US power reactors during this reporting period. Status changes at Braidwood Unit 1, Nine Mile Point 2, and Beaver Valley 2 are discussed. Other occurrences discussed are: retraining of control-room operators at Peach Bottom; a request for 25% power for Shoreham, problems at Fermi 2 which delayed the request to go to 75% power; the results of a safety study of the N Reactor at Hanford; a proposed merger of Pacific Gas and Electric with Sacramento Municipal Utility District which would result in the decommissioning of Rancho Seco; the ordered shutdown of Oyster Creek; a minor radioactivity release caused by a steam generator tube rupture at North Anna 1; and 13 fines levied by the NRC on reactor licensees

  2. Concentration of radionuclides in fresh water fish downstream of Rancho Seco Nuclear Generating Plant

    International Nuclear Information System (INIS)

    Noshkin, V.E.; Eagle, R.J.; Dawson, J.M.; Brunk, J.L.; Wong, X.M.

    1984-01-01

    Fish were collected for radionuclide analysis over a 5-month period in 1984 from creeks downstream of the Rancho Seco Nuclear Generating Plant, which has been discharging quantities of some fission and activation products to the waterway since 1981. Among the fish, the bluegill was selected for intensive study because it is very territorial and the radionuclide concentrations detected should be representative of the levels in the local environment at the downstream locations sampled. Among the gamma-emitting radionuclides routinely released, only 134 Cs and 137 Cs were detected in the edible flesh of fish. Concentrations in the flesh of fish decreased with distance from the plant. The relationship between concentration and distance was determined to be exponential. Exponential equations were generated to estimate concentrations in fish at downstream locations where no site-specific information was available. Mean concentrations of 137 Cs in bluegill collected during April, May, July and August from specific downstream stations were not significantly different in spite of the release of 131 mCi to the creeks between April and August. The concentrations in fish are not responding to changes in water concentrations brought about by plant discharges. Diet appears to be a more significant factor than size or weight or water concentration in regulating body burdens of 137 Cs in these fish

  3. Sacramento Municipal Utility district's interim onsite storage building for low level radioactive waste

    International Nuclear Information System (INIS)

    Gillis, E.

    1986-01-01

    In order to meet current and anticipated needs for the low level radwaste management program at the Rancho Seco Nuclear Generating Station, the Sacramento Municipal Utility District has a design and construction program underway which will provide an onsite interim storage facility that can be expanded in two and one-half year increments. The design approach utilized allows capital investment to be minimized and still provides radwaste management flexibility in anticipation of delays in resolution of the nationwide long term radwaste disposal situation. The facility provides storage and material accountability for all low level radwastes generated by the plant. Wastes are segregated by radioactivity level and are stored in two separate storage areas located within one facility. Lower activity wastes are stored in a lightly shielded structure and handled by lift trucks, while the higher activity wastes are stored in a highly shielded structure and handled remotely by manual bridge crane. The layout of the structure provides for economy of operation and minimizes personnel radiation exposure. Design philosophy and criteria, building layout and systems, estimated costs and construction schedule are discussed

  4. Evaluation of the miscellaneous waste evaporator at Rancho Seco

    International Nuclear Information System (INIS)

    Best, W.T.; Turney, J.H.; Gardiner, D.E.; Sacramento Municipal Utility District, Herald, CA)

    1985-01-01

    In June 1984, Sacramento Municipal Utility District gave Impell Corporation the authority to proceed with an evaluation of the operation of the miscellaneous waste evaporator. The purpose of the evaluation was to optimize the operation of the evaporator with the intent to simplify and reduce the cost of waste handling within the plant. This paper analyzes on a cost basis, several suggested solutions to achieve the above

  5. Evacuation emergency response model coupling atmospheric release advisory capability output

    International Nuclear Information System (INIS)

    Rosen, L.C.; Lawver, B.S.; Buckley, D.W.; Finn, S.P.; Swenson, J.B.

    1983-01-01

    A Federal Emergency Management Agency (FEMA) sponsored project to develop a coupled set of models between those of the Lawrence Livermore National Laboratory (LLNL) Atmospheric Release Advisory Capability (ARAC) system and candidate evacuation models is discussed herein. This report describes the ARAC system and discusses the rapid computer code developed and the coupling with ARAC output. The computer code is adapted to the use of color graphics as a means to display and convey the dynamics of an emergency evacuation. The model is applied to a specific case of an emergency evacuation of individuals surrounding the Rancho Seco Nuclear Power Plant, located approximately 25 miles southeast of Sacramento, California. The graphics available to the model user for the Rancho Seco example are displayed and noted in detail. Suggestions for future, potential improvements to the emergency evacuation model are presented

  6. 16,17-Seco- and 2,3:16,17-di-seco-pregnanes from Guarea guidonia

    Energy Technology Data Exchange (ETDEWEB)

    Garcez, Walmir Silvan; Garcez, Fernanda Rodrigues [Universidade Federal de Mato Grosso do Sul (UFMS), Campo Grande, MS (Brazil). Dept. de Quimica]. E-mail: wgarcez@nin.ufms.br; Soares, Luzinatia Ramos [Universidade Federal de Mato Grosso do Sul (UFMS), Campo Grande, MS (Brazil). Dept. de Quimica; Universidade Estadual de Mato Grosso do Sul, Campo Grande, MS (Brazil)

    2008-07-01

    Two new seco- and di-seco-pregnanes, 2{alpha},3{beta}-dihydroxy-16,17-seco-pregn-17-ene-16-oic acid methyl ester 2{beta},19-hemiketal (1) and 2,3:16,17-di-seco-pregn-17-ene-3-oic acid-16-oic acid methyl ester-19-hydroxy-2-carboxylic acid-2,19-lactone (2), have been obtained from the trunk bark of Guarea guidonia. Their structures have been established by a combination of 1D- and 2D-NMR spectroscopic techniques and MS data. The unique seco- and di-seco-pregnane carbocyclic skeletal types as found in compounds 1 and 2 are being reported in the Meliaceae for the first time as well as the occurrence of pregnanes in the genus Guarea. (author)

  7. 78 FR 76317 - Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/Fish Screen Facility Protection...

    Science.gov (United States)

    2013-12-17

    ...-FF08RSRC00] Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/ Fish Screen Facility Protection... and Wildlife (CDFW), announce that the record of decision (ROD) for the Llano Seco Riparian Sanctuary...: www.fws.gov/refuge/sacramento river/ and http://www.riverpartners.org/where-we-work/sanctuary...

  8. Spent fuel storage at the Rancho Seco Nuclear Generation Station

    International Nuclear Information System (INIS)

    Miller, K.R.; Field, J.J.

    1995-01-01

    The Sacramento Municipal Utility District (SMUD) has developed a strategy for the storage and transport of spent nuclear fuel and is now in the process of licensing and manufacturing a Transportable Storage System (TSS). Staff has also engaged in impact limiter testing, non-fuel bearing component reinsertion, storage and disposal of GTCC waste, and site specific upgrades in support of spent fuel dry storage

  9. Regulatory Experience on Structural Integrity Issues of The Oldest Reactor Pressure Vessel in Korea

    International Nuclear Information System (INIS)

    Lee, Sang-Min; Cho, Doo-Ho; Kim, Jin-Su; Kim, Yong-Beum; Chung, Hae-Dong; Kim, Se-Chang; Choi, Jae-Boong

    2015-01-01

    A reactor pressure vessel plays a crucial role of retaining reactor coolant and core assemblies. The RPV integrity should be evaluated in consideration with the design transient condition and the material deterioration of RPV belt-line region. Especially, the pressurized thermal shock has been considered as one of the most important issues regarding the RPV integrity since Rancho Seco nuclear power plant accident in 1978. In this paper, the structural integrity evaluation of the oldest RPV in Korea was performed by using finite element analysis. PTS conditions like small break loss of coolant accident and Turkey Point steam line break were applied as loading conditions. Neutron fluence data equivalent to 40 years was used to determine the fracture toughness of RPV material. The 3-dimensional finite element model including a circumferential surface flaw was considered for fracture mechanics analysis. The RPV integrity was evaluated according to Japan Electric Association Code. (authors)

  10. 78 FR 75248 - Safety Zone; Sacramento New Years Eve Fireworks Display, Sacramento River, Sacramento, CA

    Science.gov (United States)

    2013-12-11

    ... Zone; Sacramento New Years Eve Fireworks Display, Sacramento River, Sacramento, CA AGENCY: Coast Guard... safety zone in the navigable waters of the Sacramento River in Sacramento, CA on December 31, 2013 during... Sacramento River around the Tower Bridge in Sacramento, CA in approximate position 38[deg]34'49.98'' N, 121...

  11. 78 FR 75898 - Safety Zone; Sacramento New Years Eve Fireworks Display, Sacramento River, Sacramento, CA

    Science.gov (United States)

    2013-12-13

    ... Zone; Sacramento New Years Eve Fireworks Display, Sacramento River, Sacramento, CA AGENCY: Coast Guard... safety zone in the navigable waters of the Sacramento River in Sacramento, CA on December 31, 2013 during... Sacramento River around the Tower Bridge in Sacramento, CA in approximate position 38[deg]34'49.98'' N, 121...

  12. Comparison of licensing activities for operating plants designed by Babcock and Wilcox

    International Nuclear Information System (INIS)

    Thoma, J.O.

    1985-01-01

    This report provides a comparison of a number of licensing activities for the operating Babcock and Wilcox (B and W) plants with emphasis on Rancho Seco. The factors selected were a comparison of staff resources expended in FY84, active licensing action reviews, implementation of NUREG-0737 modifications, exemptions to regulations, SALP reports, enforcement actions, and Licensee Event Reports (LERs). The eight licensed operating plants examined are as follows: Arkansas Nuclear One Unit 1 (ANO-1), Crystal River Unit 3, Davis Besse, Oconee Units 1, 2, and 3, Rancho Seco, and Three Mile Island Unit 1 (TMI-1)

  13. 77 FR 75556 - Safety Zone; Sacramento New Year's Eve Fireworks Display, Sacramento River, Sacramento, CA

    Science.gov (United States)

    2012-12-21

    ... Zone; Sacramento New Year's Eve Fireworks Display, Sacramento River, Sacramento, CA AGENCY: Coast Guard... safety zones during the Sacramento New Year's Eve Fireworks Display in the navigable waters of the Sacramento River on December 31, 2012 and January 1, 2013. The fireworks displays will occur from 9 p.m. to 9...

  14. HEMISPHERIC CENTER FOR ENVIRONMENTAL TECHNOLOGY

    Energy Technology Data Exchange (ETDEWEB)

    M.A. Ebadian

    2000-01-31

    The Online Measurement of Decontamination project team received a commitment for a demonstration in May from the Sacramento (California) Municipal Utility District (SMUD) Rancho Seco site. Since this site is a member of the DOE Commercial Utilities Consortium, the demonstration will fulfill the DOE and commercial technology demonstration requirements. Discussion on deployment of the Integrated Vertical and Overhead Decontamination (IVOD) System at Rancho Seco was conducted; date for deployment tentatively scheduled for early spring. Based upon fictional requirements from SRS for a shiny monitor in a high-level waste tank, FIU-HCET developed and delivered a draft slurry monitor design and draft test plan. Experiments measuring slurry settling time for SRS slurry simulant at 10 wt% have been completed on FIU-HCET'S flow loop with SRS dip. The completed design package of the test mockup for evaluating Non-Intrusive Location of Buried Items Technologies was sent to Fluor Fernald and the Operating Engineers National Hazmat Program for review. Comments are due at the end of January. Preliminary experiments to determine size distribution of aerosols generated during metal cutting were performed. A 1/4-inch-thick iron plate was cut using a plasma arc torch, and the size distribution of airborne particles was measured using a multistage impactor. Per request of DOE-Ohio, FIU-HCET participated in a weeklong value engineering study for the characterization, decontamination, and dismantlement of their critical path facility.

  15. 78 FR 23489 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2013-04-19

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of deviation... operating regulation that governs the Tower Drawbridge across Sacramento River, mile 59.0, at Sacramento, CA... Tower Drawbridge, mile 59.0, over Sacramento River, at Sacramento, CA. The Tower Drawbridge navigation...

  16. 78 FR 15878 - Drawbridge Operation Regulations; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2013-03-13

    ... Operation Regulations; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of... operating schedule that governs the Tower Drawbridge across Sacramento River, mile 59.0, at Sacramento, CA... temporary change to the operation of the Tower Drawbridge, mile 59.0, over Sacramento River, at Sacramento...

  17. 77 FR 52599 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2012-08-30

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary... regulation that governs the Tower Drawbridge across Sacramento River, mile 59.0, at Sacramento, CA. The... change to the operation of the Tower Drawbridge, mile 59.0, over Sacramento River, at Sacramento, CA. The...

  18. ARAC feasibility study for the NRC Phase I: final report

    International Nuclear Information System (INIS)

    Rosen, L.C.; Orphan, R.C.

    1979-11-01

    The feasibility of implementing ARAC (Atmospheric Release Advisory Capability) services in a particular nuclear power plant is examined. The criteria for selecting Rancho Seco are discussed and the physical, meteorological and procedural factors related to the plant are assessed. The potential benefits and limitations of implementing ARAC at Rancho Seco are analyzed. The costs of employing the system at the nuclear power plant are given for alternative plans. A training and familiarization program is outlined

  19. 77 FR 44139 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2012-07-27

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary... Sacramento, CA. The deviation is necessary to allow the community to participate in the Fleet Feet Event, Run... Tower Drawbridge, mile 59.0, Sacramento River, at Sacramento, CA. The Tower Drawbridge navigation span...

  20. 76 FR 11960 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2011-03-04

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary..., mile 59.0, at Sacramento, CA. The deviation is necessary to allow the community to participate in the... Tower Drawbridge, mile 59.0, Sacramento River, at Sacramento, CA. The Tower Drawbridge navigation span...

  1. 77 FR 22216 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2012-04-13

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary... schedule that governs the Tower Drawbridge across the Sacramento River, mile 59.0, at Sacramento, CA. The... River, at Sacramento, CA. The Tower Drawbridge navigation span provides a vertical clearance of 30 feet...

  2. 76 FR 11679 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2011-03-03

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary..., mile 59.0, at Sacramento, CA. The deviation is necessary to allow the community to participate in the... the Tower Drawbridge, mile 59.0, Sacramento River, at Sacramento, CA. The Tower Drawbridge navigation...

  3. 76 FR 23188 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2011-04-26

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary..., mile 59.0, at Sacramento, CA. The deviation is necessary to allow the community to participate in the... Tower Drawbridge, mile 59.0, Sacramento River, at Sacramento, CA. The Tower Drawbridge navigation span...

  4. 76 FR 79067 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2011-12-21

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary..., mile 59.0, at Sacramento, CA. The deviation is necessary to allow community celebration of New Year's... Tower Drawbridge, mile 59.0, Sacramento River, at Sacramento, CA. The Tower Drawbridge navigation span...

  5. 76 FR 20843 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2011-04-14

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary..., mile 59.0, at Sacramento, CA. The deviation is necessary to allow the community to participate in the... the Tower Drawbridge, mile 59.0, Sacramento River, at Sacramento, CA. The Tower Drawbridge navigation...

  6. 77 FR 10372 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2012-02-22

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary..., mile 59.0, at Sacramento, CA. The deviation is necessary to allow the community to participate in the... Tower Drawbridge, mile 59.0, Sacramento River, at Sacramento, CA. The Tower Drawbridge navigation span...

  7. 75 FR 16006 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2010-03-31

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary..., mile 59.4, at Sacramento, CA. The deviation is necessary to allow the bridge owner to make bridge... Sacramento River, at Sacramento, CA. The I Street Drawbridge navigation span provides 109 feet vertical...

  8. 76 FR 26181 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2011-05-06

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary... 59.0, at Sacramento, CA. The deviation is necessary to allow the community to participate in the Hope... Drawbridge, mile 59.0, over Sacramento River, at Sacramento, CA. The drawbridge navigation span provides a...

  9. 77 FR 10371 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2012-02-22

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of temporary..., mile 59.0, at Sacramento, CA. The deviation is necessary to allow the bridge owner to conduct... change to the operation of the Tower Drawbridge, mile 59.0, Sacramento River, at Sacramento, CA. The...

  10. Evolution of an outage management organization in a small utility

    International Nuclear Information System (INIS)

    Oubre, R.P.; Shetler, J.

    1985-01-01

    Six refueling outages with a number of major equipment failure outages have taught Rancho Seco management three main items. One is that a dedicated management organization must be formed for the purpose of controlling work functions at Rancho Seco. This dedicated organization must have the experience of the plant and not have the responsibility for the actual maintenance. Second, upper management within a power plant must get directly involved in the outage. Upper management must show their presence, give input, and be available when needed. The third item learned is that the scheduling organization must be adequately staffed. Although Rancho Seco completed a refueling outage in 1978 within only 36 days, additional inspection requirements due to regulatory changes and/or previous equipment failures requiring follow-up actions would place the shortest possible outage today at approx.70 days. The only way an organization can keep this outage time down is with the proper scheduling of the resources and the timely coordination of activities to reduce conflicts

  11. 78 FR 15879 - Drawbridge Operation Regulations; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2013-03-13

    ... Operation Regulations; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of... operating regulation that governs the Tower Drawbridge across the Sacramento River, mile 59.0, at Sacramento, CA. The deviation is necessary to allow the community to participate in the First Annual ``Biggest...

  12. 78 FR 42452 - Drawbridge Operation Regulation; Sacramento River, Sacramento, CA

    Science.gov (United States)

    2013-07-16

    ... Operation Regulation; Sacramento River, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION: Notice of deviation... Sacramento, CA. The deviation is necessary to allow the bridge owner to make bridge repairs. This deviation... Sacramento, CA. The drawbridge navigation span provides 109 feet vertical clearance above Mean High Water in...

  13. 76 FR 81827 - Safety Zone; Sacramento New Years Eve Fireworks Display, Sacramento, CA

    Science.gov (United States)

    2011-12-29

    ... Zone; Sacramento New Years Eve Fireworks Display, Sacramento, CA AGENCY: Coast Guard, DHS. ACTION... during the Sacramento New Years Eve Fireworks Display in the navigable waters of the Sacramento River... Sacramento New Years Eve Fireworks Display safety zones in the navigable waters of the Sacramento River near...

  14. Atmospheric release advisory capability pilot project at two nuclear power plants and associated state offices of emergency preparedness. Final report

    International Nuclear Information System (INIS)

    Rosen, L.C.

    1983-01-01

    A project to demonstrate the feasibility of utilizing Atmospheric Release Advisory Capability (ARAC) limited service with commercial nuclear power plants and their associated state offices of emergency preparedness is discussed. Preliminary planning, installation and testing of the ARAC site facilities at Indian Point Nucler Power Station, New York State; at New York State Office of Emergency Preparedness, Albany, New York; at Rancho Seco Nuclear Generating Station, California; and at the State of California Office of Emergency Services, Sacramento, California, are summarized. ARAC participation in the Robert E. Ginna nuclear generating plant accident in New York on January 25, 1982, is discussed. The ARAC system is evaluated with emphasis on communications, the suite of models contained within the ARAC system, and the staff. The implications of this project in designing the next-generation ARAC system to service federal and state needs are assessed

  15. Total Synthesis of Two 4, 5-Dioxo-seco-eudesmane Sesquiterpenes

    Institute of Scientific and Technical Information of China (English)

    Li Jing FANG; Chen Xi ZHANG; Jin Chun CHEN; Guo Jun ZHENG; Yu Lin LI

    2005-01-01

    A facile synthetic route to two seco-eudesmane, 4, 5-dioxo-10-epi-4, 5-seco-γeudesmane (1) and 4, 5-dioxo-10-epi-4, 5-seco-γ-eudesmol (2) from (+)-dihydrocarvone has been described. Avoiding expensive reagents, this highly economic method especially suits for the synthesis of 4, 5-seco-eudesman-type and ophianon-type sesquiterpenes with a double bond at position 11 and 12.

  16. Occurrence and biogenesis of seco-triterpenoids

    DEFF Research Database (Denmark)

    Almeida Robles, Aldo Ricardo

    Triterpenoids are secondary metabolites synthesized by oxidosqualene cyclases (OSCs), a class of enzyme that converts the linear squalene-2,3-oxide to single or multi-ring products in a dynamic process called cyclization. The cyclization cascade is powered by a migrating carbocation that through...... process of an OSC or from post cyclization modification steps. The bioactivity and biosynthesis of the seco-triterpenoids is intriguing, and yet underexplored. In this thesis a review of structure-activity relationships of seco-triterpenoids is presented. Seco-cycloartanes report the highest cytotoxicity...... OSCs in O. spinosa (OsONS1 and OsONS2) which both are able to produce α-onocerin. Contrary to the α-onocerin pathway in L. clavatum in which two different cyclases are needed for α-onocerin synthesis. Moreover, an OSC phylogenetic analysis indicated the onocerin synthases of O. spinosa arose from...

  17. Nuclear Regulatory Commission Issuances, May 81

    International Nuclear Information System (INIS)

    1981-05-01

    Contents: Issuances of the Nuclear Regulatory Commission--Consolidated Edison Company of New York, Inc. (Indian Point, Unit No. 2), Power Authority of the State of New York (Indian Point, No. 3 Nuclear Power Plant), Pacific Gas and Electric Company (Diablo Canyon Nuclear Power Plant, Units 1 and 2), Statement of Policy on Conduct of Licensing Proceedings, Uranium Mill Licensing Requirements; Issuances of Atomic Safety and Licensing Appeal Boards--Houston Lighting and Power Company, et al. (South Texas Project, Units 1 and 2), Metropolitan Edison Company, et al. (Three Mile Island Nuclear Station, Unit No. 2), Pennsylvania Power and Light Company and Allegheny Electric Cooperative, Inc. (Susquehanna Steam Electric Station, Units 1 and 2), Philadelphia Electric Company et al. (Peach Bottom Atomic Power Station, Units 2 and 3), Public Service Electric and Gas Company (Hope Creek Generating Station, Units 1 and 2); Issuances of the Atomic Safety and Licensing Boards--Duke Power Company (William B. McGuire Nuclear Station, Units 1 and 2), Florida Light and Power Company (Turkey Point Nuclear Generating, Units 3 and 4), Illinois Power Company, et al. (Clinton Power Station, Units 1 and 2), Sacramento Municipal Utility District (Rancho Seco Nuclear Generating Station); Issuances of the Directors Denial--Commonwealth Edison Company (Byron Station, Units 1 and 2), Consolidated Edison Company of New York, Inc. (Indian Point Unit No. 2), Gulf States Utilities Company (River Bend Station Units 1 and 2), Petition to Suspend All Operating Licenses for Pressurized Water Reactors (River Bend Station Units 1 and 2), Portland General Electric Company (Trojan Nuclear

  18. 77 FR 40800 - Safety Zone: Sacramento River Closure for Aerial Cable Installation, Sacramento, CA

    Science.gov (United States)

    2012-07-11

    ...-AA00 Safety Zone: Sacramento River Closure for Aerial Cable Installation, Sacramento, CA AGENCY: Coast... zone in the navigable waters of the Sacramento River near Sherman Island, CA in support of the...; Sacramento River Closure for Aerial Cable Installation, Sacramento, CA. (a) Location. This temporary safety...

  19. A novel 1,10-seco withanolide from Physalis peruviana.

    Science.gov (United States)

    Fang, Sheng-Tao; Liu, Ji-Kai; Li, Bo

    2010-07-01

    A novel 1,10-seco withanolide, 1,10-seco withaperuvin C (1), together with four known withanolides, 4 beta-hydroxywithanolide E (2), visconolide (3), withanolide F (4), and withaphysanolide (5), was isolated from the aerial parts of Physalis peruviana. The structures of compounds 1-5 were determined on the basis of spectroscopic methods including extensive 1D and 2D NMR analysis. In addition, the possible biogenetic relationships among these five withanolides are discussed.

  20. A municipal utility seeks IPP power

    International Nuclear Information System (INIS)

    Whitney, D.D.

    1990-01-01

    The Sacramento Municipal Utility District (SMUD), primarily located in Sacramento County, one of the ten highest growth areas in the U.S. today, serves a 900 square mile area with over 450,000 customers and has seen peak loads of about 2200 MW. In June of 1989, the customer-owners of SMUD, voted to shutdown the 913 MW Rancho Seco Nuclear Generating Station which constituted nearly one-half of the district's power resources. The need to immediately replace the lost capacity was somewhat tempered as a consequence of previously signed contracts with the Pacific Gas and Electric Company (PG and E) for 550 MW and with the Southern California Edison Company (SCE) for 300 MW. Both contracts provide power for only ten years, ending in 1999, and while being competitively priced in the early years, include significant escalation in capacity charges beginning in 1995, and always price energy at local natural gas market prices while including other arduous conditions. When combined with their hydroelectric and other resources these contracts allow SMUD to remain competitive. However, there remains the incentive, and ultimately necessity, of replacing the contracts with alternative resources. This paper describes an aggressive program to obtain replacement resources which will diversify SMUD's resource mix and protect their customer-owners from the uncertainties of the future while retaining the benefits of tax exempt financing and being their own stockholders

  1. Verticillarone: a new seco-fusicoccane diterpenoid ketonepoxide from Hypoestes verticillaris.

    Science.gov (United States)

    Al-Rehaily, Adnan J; Al-Yahya, M A; Mirza, Humayun H; Ahmed, Bahar

    2002-06-01

    The aerial parts of Hypoestes verticillaris (L.F.) Sol. (Acanthaceae) has afforded a new seco-fusicoccane diterpenoid ketonepoxide, which was characterized as 1(10) seco-fusicocc-3 (4)-ene-5, 11, 14-trione-8 (9), 1 (7)-diepoxide (1) on the basis of spectral analysis and named as verticillarone, along with earlier reported diterpenoid, i.e. 13-hydroxy-7-oxo-labda-8, 14-diene (2).

  2. 76 FR 14052 - Notice of Inventory Completion: California State University, Sacramento, Sacramento, CA

    Science.gov (United States)

    2011-03-15

    ... Sacramento County, CA, during a test excavation project. The Far Western Anthropological Research Group Inc... from ethnohistoric and ethnographic sources indicate that the site was most likely occupied by Nisenan... the Sacramento River and Miwok-speakers resided south of the American River. Ethnographic data and...

  3. Diffusion near buildings as determined from atmospheric tracer experiments. Technical report

    Energy Technology Data Exchange (ETDEWEB)

    Sagendorf, J.F.; Ricks, N.R.; Start, G.E.; Dickson, C.R.

    1980-09-01

    Data from the innermost arcs and roof top samplers of the Rancho Seco and EOCR field studies were used to examine diffusion close to a building. The minimum length plume paths were determined from each release location to each sampler position at these two test sites. Measured concentrations, normalized by source strength (C/Q), were plotted versus plume path length and an envelope containing 95% of the measured values of C/Q was determined. The curves from the two sites were similar in shape and implied three zones of diffusion. Comparisons were also made with current NRC methods for predicting maximum expected concentrations close to a building. The NRC model overestimated concentrations in all but one case. The model was generally within an order of magnitude at EOCR, and within two orders of magnitude at Rancho Seco.

  4. Sacramento Metropolitan Area, California

    Science.gov (United States)

    1992-02-01

    addition, several Federal candidate species, the California Hibiscus , California tiger salamander, Sacramento Anthicid Beetle, Sacramento Valley tiger...Board, California Waste Management Board, and Department of Health Services contribute to this list. The Yolo County Health Services Agency maintains and...operation and maintenance of the completed recreational facility. Recreation development is limited to project lands unless health and safety

  5. From Allá en el Rancho Grande to Lola la trailera: social mobility

    Directory of Open Access Journals (Sweden)

    Aurelio de los Reyes

    2016-04-01

    Full Text Available The text deals with both horizontal and vertical social mobility in the Mexican films Allá en el Rancho Grande (1936, Fernando de Fuentes, Por la puerta falsa (1950, Fernando de Fuentes, Nosotras las taquígrafas (1950, Emilio Gómez Muriel, El río y la muerte (1954, Luis Buñuel, three films by Emilio Fernández: Victimas del pecado (1950, Salón México (1948 and Las abandonadas (1944, two films by Ismael Rodríguez: La Cucaracha (1958 and Del rancho a la televisión (1952 and Lola la trailera (1984, Raúl Fernández, which speaks to the country’s transition from an agricultural to an industrial economy.

  6. Caracterización de ranchos ganaderos de Campeche, México. Resultados de proyectos de transferencia de tecnologías

    Directory of Open Access Journals (Sweden)

    Aslam Díaz Castillo

    2014-01-01

    Full Text Available Se caracterizaron 24 ranchos ganaderos de Campeche, México. Se evaluó la transferencia de tecnologías en proyectos de producción de leche, carne bovina y pastos, durante 2012. Predominaron los propietarios con educación primaria (33.33%. El 55.40% del área tenía pastos cultivados y el 0.41% forrajes para la época poco lluviosa. El 8.33% fabricaban alimentos. El 50% tenía cerco eléctrico, con 1.28 unidades de ganado mayor. hectárea-1. Las vacas representaron el 64.01% de las hembras; las novillas de 2 años al parto, el 18.12%; del nacimiento al año, el 12.80%, y de 1-2 años, el 5.07%. En el hato predominaron: el Cebú (33.33% y Suizo pardo (29.17%, y en los sementales Mestizos de Holstein (25% y Beef master (20%, con 35 reproductoras. semental-1. Se utilizaron 4 de las 8 vacunas recomendadas en el estado. La mortalidad anual en crías fue del 10.23%. El 66.67% de los productores tenían registros de salud, 41.67% de movimiento del hato, 33.33% de reproducción, 25% de producción y 8.33% de economía. Se capacitaron 2,487 productores y se establecieron 10 ranchos tecnológicos demostrativos. Se logró el uso de controles técnicos, cerco eléctrico y alimentos elaborados en todos los ranchos. Se plantaron 54 hectáreas de Pennistum purpureum variedad cultivar Cuba CT-115, 15.50 hectáreas de Cuba OM-22 y 0.50 hectáreas de Cuba CT-169. Se incrementó la producción láctea en 60,000 litros de enero-agosto, respecto a igual período de 2011; y alcanzó 1 kilogramo. animal-1. día-1 en 2 ciclos sucesivos de ceba en estabulación, en ranchos de productores líderes.

  7. Aplicação da Cadeia de Markov para Dias Secos e Chuvosos

    Directory of Open Access Journals (Sweden)

    André Luiz de Carvalho

    Full Text Available Resumo A precipitação é um fenômeno meteorológico importante na região Tropical, caracterizada por sua variabilidade espacial-temporal e eventos extremos associados. Assim, a informação prévia da ocorrência de um dia ser seco ou chuvoso é de extrema importância para diversas atividades humanas, em especial a agricultura. O objetivo desse trabalho foi analisar a ocorrência de dias secos e chuvosos na região de Rio Largo–Alagoas, por meio da Cadeia de Markov. Dados diários de precipitação entre 1973 e 2008 foram utilizados. Na definição de dias secos e chuvosos consideraram-se seis limites de precipitação e, aplicou-se a Cadeia de Markov, para identificar as probabilidades de ocorrências condicionais de dias secos e chuvosos. A região de estudo apresentou estações seca (setembro a março e chuvosa (abril a agosto melhor definidas, considerados valores limites de precipitação entre 0 e 2 mm. Maior ocorrência de dias secos e chuvosos ocorreu de novembro a dezembro (94% e junho a julho (84%, respectivamente. A Cadeia de Markov permitiu concluir que a transição entre dias secos e chuvosos é baixa ao longo do ano.

  8. Metals transport in the Sacramento River, California, 1996-1997; Volume 2: Interpretation of metal loads

    Science.gov (United States)

    Alpers, Charles N.; Antweiler, Ronald C.; Taylor, Howard E.; Dileanis, Peter D.; Domagalski, Joseph L.

    2000-01-01

    Metals transport in the Sacramento River, northern California, from July 1996 to June 1997 was evaluated in terms of metal loads from samples of water and suspended colloids that were collected on up to six occasions at 13 sites in the Sacramento River Basin. Four of the sampling periods (July, September, and November 1996; and May-June 1997) took place during relatively low-flow conditions and two sampling periods (December 1996 and January 1997) took place during high-flow and flooding conditions, respectively. This study focused primarily on loads of cadmium, copper, lead, and zinc, with secondary emphasis on loads of aluminum, iron, and mercury.Trace metals in acid mine drainage from abandoned and inactive base-metal mines, in the East and West Shasta mining districts, enter the Sacramento River system in predominantly dissolved form into both Shasta Lake and Keswick Reservoir. The proportion of trace metals that was dissolved (as opposed to colloidal) in samples collected at Shasta and Keswick dams decreased in the order zinc ≈ cadmium > copper > lead. At four sampling sites on the Sacramento River--71, 256, 360, and 412 kilometers downstream of Keswick Dam--trace-metal loads were predominantly colloidal during both high- and low-flow conditions. The proportion of total cadmium, copper, lead, and zinc loads transported to San Francisco Bay and the Sacramento-San Joaquin Delta estuary (referred to as the Bay-Delta) that is associated with mineralized areas was estimated by dividing loads at Keswick Dam by loads 412 kilometers downstream at Freeport and the Yolo Bypass. During moderately high flows in December 1996, mineralization-related total (dissolved + colloidal) trace-metal loads to the Bay-Delta (as a percentage of total loads measured downstream) were cadmium, 87 percent; copper, 35 percent; lead, 10 percent; and zinc, 51 percent. During flood conditions in January 1997 loads were cadmium, 22 percent; copper, 11 percent; lead, 2 percent; and zinc, 15

  9. Reinterpretation of the stratigraphy and structure of the Rancho Las Norias area, central Sonora, Mexico

    Science.gov (United States)

    Page, W.R.; Harris, A.G.; Poole, F.G.; Repetski, J.E.

    2003-01-01

    New geologic mapping and fossil data in the vicinity of Rancho Las Norias, 30 km east of Hermosillo, Sonora, Mexico, show that rocks previously mapped as Precambrian instead are Paleozoic. Previous geologic maps of the Rancho Las Norias area show northeast-directed, southwest-dipping reverse or thrust faults deforming both Precambrian and Paleozoic rocks. The revised stratigraphy requires reinterpretation of some of these faults as high-angle normal or oblique-slip faults and the elimination of other faults. We agree with earlier geologic map interpretations that compressional structures have affected the Paleozoic rocks in the area, but our mapping suggests that the direction of compression is from southeast to northwest. Published by Elsevier Ltd.

  10. Measured performance of four PWR liquid radioactive waste treatment systems

    International Nuclear Information System (INIS)

    McIsaac, C.V.; Mandler, J.W.; Stalker, A.C.

    1980-01-01

    This paper presents results of a study of the liquid radwaste treatment and boron recovery systems of four operating PWR power plants. The performance of a given system was determined from measurements of radionuclide inventories in samples drawn from demineralizers, evaporators, filters, and gaseous cleanup systems. The plants at which measurements were made are Fort Calhoun, Zion 1 and 2, Turkey Point 3 and 4, and Rancho Seco

  11. 75 FR 81642 - Long-Term North to South Water Transfer Program, Sacramento County, CA

    Science.gov (United States)

    2010-12-28

    ..., Sacramento County, CA AGENCY: Bureau of Reclamation, Interior. ACTION: Notice of intent to prepare an...., Chico, CA. Wednesday, January 12, 2011, 2-4 p.m., Sacramento, CA. Thursday, January 13, 2011, 6-8 p.m..., MP-410, Sacramento, CA 95825. Scoping meetings will be held at: Chico at the Chico Masonic Family...

  12. Spectroscopical analysis and molecular mechanics calculation of 8,9-Seco-lanostane; Analise espectroscopica e calculos de mecanica molecular de 8,9-seco-lanostanos

    Energy Technology Data Exchange (ETDEWEB)

    Rehder, Vera G; Fujiwara, Fred Y; Marsaioli, Anita J [Universidade Estadual de Campinas, SP (Brazil). Inst. de Quimica

    1992-12-31

    8.9-Seco-lanostane derivatives have been synthesized visualizing their application as intermediates in chiral building block syntheses and we are here presenting their spectroscopy analyses and MM2 molecular mechanic calculations. (author) 5 refs., 4 figs.

  13. Integrity of PWR pressure vessels during overcooling accidents

    International Nuclear Information System (INIS)

    Cheverton, R.D.; Iskander, S.K.; Whitman, G.D.

    1982-01-01

    The reactor pressure vessel in a pressurized water reactor is normally subjected to temperatures and pressures that preclude propagation of sharp, crack-like defects that might exist in the wall of the vessel. However, there is a class of postulated accidents, referred to as overcooling accidents, that can subject the pressure vessel to severe thermal shock while the pressure is substantial. As a result of such accidents vessels containing high concentrations of copper and nickel, which enhance radiation embrittlement, may possess a potential for extensive propagation of preexistent inner surface flaws prior to the vessel's normal end of life. For the purpose of evaluating this problem a state-of-the-art fracture mechanics model was developed and has been used for conducting parametric analyses and for calculating several recorded PWR transients. Results of the latter analysis indicate that there may be some vessels that have a potential for failure today if subjected to a Rancho Seco (1978) or TMI-2 (1979) type transient. However, the calculational model may be excessively conservative, and this possibility is under investigation

  14. Rancho Seco Nuclear Generating Station, Unit 1. Annual report for 1976

    International Nuclear Information System (INIS)

    1977-03-01

    Net electrical energy generated was 2,205,091 MWH with the generator on line 2,662 hrs. Information is presented concerning operations, changes, tests, maintenance, fuel performance, refueling, shutdowns and outages, containment local leak rate testing, and power generation

  15. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J.; Best, Ralph E.; Ross, Steven B.; Buxton, Kenneth A.; England, Jeffery L.; McConnell, Paul E.

    2013-09-30

    This report fulfills the M2 milestone M2FT-13PN0912022, “Stranded Sites De-Inventorying Report.” In January 2013, the U.S. Department of Energy (DOE) issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (DOE 2013). Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. This focus is consistent with the recommendations of the Blue Ribbon Commission on America’s Nuclear Future, which identified removal of stranded used nuclear fuel at shutdown sites as a priority so that these sites may be completely decommissioned and put to other beneficial uses (BRC 2012). Shutdown sites are defined as those commercial nuclear power reactor sites where the nuclear power reactors have been shut down and the site has been decommissioned or is undergoing decommissioning. In this report, a preliminary evaluation of removing used nuclear fuel from 12 shutdown sites was conducted. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, and San Onofre. These sites have no other operating nuclear power reactors at their sites and have also notified the U.S. Nuclear Regulatory Commission that their reactors have permanently ceased power operations and that nuclear fuel has been permanently removed from their reactor vessels. Shutdown reactors at sites having other operating reactors are not included in this evaluation.

  16. The synthesis and pharmacological evaluation of (±-2,3-seco-fentanyl analogues

    Directory of Open Access Journals (Sweden)

    LJ. DOSEN-MICOVIC

    2004-11-01

    Full Text Available An efficient, five-step synthetic approach to various acyclic 1,3-diamines has been developed and applied to the preparation of a novel class of open-chained fentanyl analogues. The acyclic derivatives 5.1–5.5 (all new compounds were synthesized with the aim of estimating the significance of the piperidine ring for the opioid analgesic activity of anilido-piperidines. The starting b-keto-amide 1.1, prepared by the aminolysis of methyl acetoacetate with methylphenethylamine, (93 % yield, was successively reacted with NaH and BuLi, to form the highly reactive a,g-dienolate anion 1.1a. Regio and chemoselective g-alkylation of the dienolate with various primary and secondary alkyl halides furnished the b-keto-amides 1.2–1.5 (76–91 %. Reductive amination of the keto-amides 1.1–1.5 with aniline and Zn powder in acetic acid, via the enamine intermediates 2.1–2.5, afforded the b-anilino amides 3.1–3.5 (74–85 %. After reductive deoxygenation of the tertiary amide group, using in situ generated diborane, the corresponding 1,3-diamines 4.1–4.5 were obtained (87–97 %. The synthesis of (±-2,3-seco-fentanyls 5.1–5.5 was completed by N-acylation of the diamines 4.1–4.5 with propionyl chloride, followed by precipitation of the monooxalate salts (86–95 %. The parent compound, 2,3-seco-fentanyl 5.1, was found to be a 40 times less potent narcotic analgesic than fentanyl but still 5–6 times more active than morphine in rats, while i-Pr derivative 5.3 was inactive. Apart from the pharmacological significance, the general procedure described herein may afford various functionalized, 1,3-diamines as potential complexing agents and building blocks for the synthesis of aza-crown ethers.

  17. 77 FR 45575 - Foreign-Trade Zone 143-West Sacramento, CA

    Science.gov (United States)

    2012-08-01

    ... Sacramento, CA Application for Extended Production Authority; Subzone 143D, Grafil Inc. (Carbon Fiber Production); Sacramento, California An application has been submitted to the Foreign-Trade Zones Board (the... its facilities located in Sacramento, California. The application conforming to the requirements of...

  18. Plantas transgénicas con alto rendimiento en peso seco y almidón cuyos órganos de reserva presentan elevada textura, elevado contenido en almidón y elevado rendimiento en peso seco

    OpenAIRE

    Pozueta Romero, Javier; Alonso Casajús, Nora; Muñoz Pérez, Francisco José; Baroja-Fernández, Edurne

    2007-01-01

    Plantas transgénicas con alto rendimiento en peso seco y almidón cuyos órganos de reserva presentan elevada textura, elevado contenido en almidón y elevado rendimiento en peso seco. La presente invención proporciona plantas transgénicas con alto rendimiento en peso seco y almidón cuyos órganos de reserva presentan elevada textura, elevado contenido en almidón y elevado rendimiento en peso seco.

  19. OS SACRAMENTAIS, SACRAMENTOS DOS POBRES

    Directory of Open Access Journals (Sweden)

    Victor Codina

    1990-01-01

    Full Text Available Basta ter tido um pouco de experiência pastoral com setores populares, concretamente na América Latina, para constatar a importância dos sacramentais na vida cristã do povo. Além das manifestações de piedade popular que se costuma estudar sob a rubrica de religiosidade popular (peregrinações, festas de padroeiro, procissões..., gostaria de destacar aqui outros elementos mais estreitamente ligados ao mundo dos sacramentos, ainda que não formem parte dos sete sacramentos tridentinos.

  20. 76 FR 3157 - Joint Operations Center Relocation Project, Sacramento County, CA

    Science.gov (United States)

    2011-01-19

    ..., Sacramento County, CA AGENCY: Bureau of Reclamation, Interior. ACTION: Notice of intent to prepare an... Reclamation, 2800 Cottage Way, Sacramento, CA 95825 or e-mail [email protected] . The public scoping meetings... construct a new JOC in the Sacramento area to be occupied by June 2015. The new JOC would provide typical...

  1. The seco-iridoid pathway from Catharanthus roseus

    NARCIS (Netherlands)

    Miettinen, K.; Dong, L.; Navrot, N.; Burlat, V.; Schneider, T.; Pollier, J.; Woittiez, L.S.; Krol, van der A.R.; Lugan, R.; Llc, T.; Verpoorte, R.; Oksman-Caldentey, K.M.; Martinoia, E.; Bouwmeester, H.J.

    2014-01-01

    The (seco)iridoids and their derivatives, the monoterpenoid indole alkaloids (MIAs), form two large families of plant-derived bioactive compounds with a wide spectrum of high-value pharmacological and insect-repellent activities. Vinblastine and vincristine, MIAs used as anticancer drugs, are

  2. Sacramento District History (1929-2004)

    National Research Council Canada - National Science Library

    Collins, Willie; Asay, Laura; Davy, Barbara J; Doyle, Brian; Fast, James P; Gonzalez, Jennifer L; Layton, Debra A; Nevins, Michael J; Taylor, James H; Van Dam, Carl

    2004-01-01

    Although the Sacramento District was established in 1929, this document recaptures the legendary history from the mid-1800's and the repercussions the Central Valley endured regarding the navigation...

  3. 77 FR 24252 - Notice of Release From Federal Grant Assurance Obligations for Sacramento International Airport...

    Science.gov (United States)

    2012-04-23

    ... Assurance Obligations for Sacramento International Airport (SMF), Sacramento, CA AGENCY: Federal Aviation... of land comprising approximately 6.50 acres of airport property at the Sacramento International Airport, California. The County of Sacramento proposes to release the 6.50 acres for sale to the...

  4. 75 FR 20598 - Public Buildings Service; Prospect Island, Sacramento Delta, Solano County, CA; Transfer of Property

    Science.gov (United States)

    2010-04-20

    ... GENERAL SERVICES ADMINISTRATION [Wildlife Order 188; 9-I-CA-1674] Public Buildings Service; Prospect Island, Sacramento Delta, Solano County, CA; Transfer of Property Pursuant to section 2 of Public... General Services Administration transferred 1253 acres of land identified as Prospect Island, Sacramento...

  5. Ground-water quality in the southeastern Sacramento Valley aquifer, California, 1996

    Science.gov (United States)

    Milby Dawson, Barbara J.

    2001-01-01

    In 1996, the U.S. Geological Survey sampled 29 domestic wells and 2 monitoring wells in the southeastern Sacramento Valley as part of the U.S. Geological Survey's National Water-Quality Assessment (NAWQA) Program. This area, designated as the NAWQA Sacramento subunit study area, was chosen because it had the largest amount of ground-water use in the Sacramento River Basin. The Sacramento subunit study area is about 4,400 square kilometers and includes intense agricultural and urban development. The wells sampled ranged from 14.9 to 79.2 meters deep. Ground-water samples from 31 wells were analyzed for 6 field measurements, 14 inorganic constituents, 6 nutrient constituents, organic carbon, 86 pesticides, 87 volatile organic compounds, tritium (hydrogen-3), radon-222, deuterium (hydrogen-2), and oxygen-18. Nitrate levels were lower than the 2000 drinking-water standards in all but one well, but many detections were in the range that indicated an effect by human activities on ground-water quality. Radon was detected in all wells, and was measured at levels above the proposed Federal 2000 maximum contaminant level in 90 percent of the wells. Five pesticides and one pesticide degradation product were detected in ground-water samples and concentrations were below 2000 drinking-water standards. All pesticides detected during this study have been used in the Sacramento Valley. Thirteen volatile organic compounds were detected in ground water. One detection of trichloroethene was above Federal 2000 drinking-water standards, and another, tetrachloromethane, was above California 1997 drinking-water standards; both occurred in a well that had eight volatile organic compound detections and is near a known source of ground-water contamination. Pesticides and volatile organic compounds were detected in agricultural and urban areas; both pesticides and volatile organic compounds were detected at a higher frequency in urban wells. Ground-water chemistry indicates that natural

  6. Independent assessment of TRAC-PD2 and RELAP5/MOD1 codes at BNL in FY 1981

    International Nuclear Information System (INIS)

    Saha, P.; Jo, J.H.; Neymotin, L.; Rohatgi, U.S.; Slovik, G.

    1982-12-01

    This report documents the independent assessment calculations performed with the TRAC-PD2 and RELAP/MOD1 codes at Brookhaven National Laboratory (BNL) during Fiscal Year 1981. A large variety of separate-effects experiments dealing with (1) steady-state and transient critical flow, (2) level swell, (3) flooding and entrainment, (4) steady-state flow boiling, (5) integral economizer once-through steam generator (IEOTSG) performance, (6) bottom reflood, and (7) two-dimensional phase separation of two-phase mixtures were simulated with TRAC-PD2. In addition, the early part of an overcooling transient which occurred at the Rancho Seco nuclear power plant on March 20, 1978 was also computed with an updated version of TRAC-PD2. Three separate-effects tests dealing with (1) transient critical flow, (2) steady-state flow boiling, and (3) IEOTSG performance were also simulated with RELAP5/MOD1 code. Comparisons between the code predictions and the test data are presented

  7. Integrity of PWR pressure vessels during overcooling accidents

    International Nuclear Information System (INIS)

    Cheverton, R.D.; Iskander, S.K.; Whitman, G.D.

    1982-01-01

    The reactor pressure vessel in a pressurized water reactor is normally subjected to temperatures and pressures that preclude propagation of sharp, crack-like defects that might exist in the wall of the vessel. However, there is a class of postulated accidents, referred to as overcooling accidents, that can subject the pressure vessel to severe thermal shock while the pressure is substantial. As a result of such accidents, vessels containing high concentrations of copper and nickel, which enhance radiation embrittlement, may possess a potential for extensive propagation of preexistent inner surface flaws prior to the vessel's normal end of life. A state-of-the-art fracture-mechanics model was developed and has been used for conducting parametric analyses and for calculating several recorded PWR transients. Results of the latter analysis indicate that there may be some vessels that have a potential for failure in a few years if subjected to a Rancho Seco-type transient. However, the calculational model may be excessively conservative, and this possibility is under investigation

  8. 1997 Sacramento Inland Floodplain Lidar

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This data set includes data collected in October 1997 over the Sacramento, CA, floodplain. Laser mapping uses a pulsed laser ranging system mounted onboard an...

  9. 78 FR 53270 - Revision of Air Quality Implementation Plan; California; Sacramento Metropolitan Air Quality...

    Science.gov (United States)

    2013-08-29

    ... Quality Implementation Plan; California; Sacramento Metropolitan Air Quality Management District... to the Sacramento Metropolitan Air Quality Management District (SMAQMD or District) portion of the..., Sacramento Metropolitan Air Quality Management District, Rule 214 (Federal New Source Review), Rule 203...

  10. Síndrome seco - Síndrome de Sjögren

    OpenAIRE

    Cañas Dávila, Carlos Alberto

    2002-01-01

    ¿Qué es el "síndrome seco"?/ ¿Qué es el síndrome Sjögren?/ ¿Qué es un síndrome de Sjögren primario y qué es un síndrome de Sjögren secundario?/ ¿Cuáles son las causas del síndrome de Sjögren?/ ¿Qué otras manifestaciones distintas a los síntomas secos puede ocasionar el síndrome de Sjögren?/ ¿Cómo se diagnostica un síndrome de Sjögren?/ ¿Cuál es el tratamiento del síndrome de Sjögren?/ ¿Qué tan frecuente es el síndrome de Sjögren?

  11. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Federal Railroad Administration (FRA) (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2014-10-01

    visits. Every site was found to have at least one off-site transportation mode option for removing its UNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. Additional conclusions from this evaluation include: The 12 shutdown sites use designs from 4 different suppliers involving 9 different (horizontal and vertical) dry storage systems that would require the use of 8 different transportation cask designs to remove the UNF and GTCC waste from the shutdown sites; Although there are common aspects, each site has some unique features and/or conditions; Although some regulatory actions will be required, all UNF at the initial 9 shutdown sites (Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, and Zion) is in licensed systems that can be transported, including a small amount of high-burnup fuel; Each site indicated that 2-3 years of advance time would be required for its preparations before shipments could begin; Most sites have more than one transportation option, e.g., rail, barge, or heavy haul truck, as well as constraints and preferences. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.

  12. A comparison of the herpetofaunas of Ranchos Los Fresnos and El Aribabi in northern Sonora, Mexico

    Science.gov (United States)

    James C. Rorabaugh; Jeffrey M. Servoss; Valerie L. Boyarski; Erin Fernandez; Doug Duncan; Carlos Robles Elias; Kevin E. Bonine

    2013-01-01

    To compare and contrast herpetofaunas at Ranchos Los Fresnos and El Aribabi in north-central Sonora, México, we conducted herpetological surveys during 2006-2011, contacted others working in these two areas, and queried 27 museums and collections for specimens collected at or near these ranches. Based on this work, nine and seven amphibian, and 27 and 24 reptile...

  13. Structural Necessity of Indole C5-O-Substitution of seco-Duocarmycin Analogs for Their Cytotoxic Activity

    Directory of Open Access Journals (Sweden)

    Taeyoung Choi

    2010-11-01

    Full Text Available A series of racemic indole C5-O-substituted seco-cyclopropylindole (seco-CI compounds 1-5 were prepared by coupling in the presence of EDCI of 1-(tert-butyloxycarbonyl-3-(chloromethylindoline (seg-A with 5-hydroxy-, 5-O-methylsulfonyl, 5-O-aminosulfonyl, 5-O-(N,N-dimethylaminosulfonyl- and 5-O-benzyl-1H-indole-2-carboxylic acid as seg-B. Compounds 1-5 were tested for cytotoxic activity against four human cancer cell lines (COLO 205, SK-MEL-2, A549, and JEG-3 using a MTT assay. Compounds 2 and 3 with small sized sulfonyl substituents like 5-O-methylsulfonyl and 5-O-aminosulfonyl exhibit a similar level of activity as doxorubicin against all cell lines tested.

  14. Timber resource statistics for the Sacramento resource area of California.

    Science.gov (United States)

    Karen L. Waddell; Patricia M. Bassett

    1997-01-01

    This report is a summary of timber resource statistics for the Sacramento Resource Area of California, which includes Butte, Colusa, El Dorado, Glenn, Lake, Napa, Nevada, Placer, Plumas, Sacramento, Sierra, Sutter, Tehama, Yolo, and Yuba Counties. Data were collected as part of a statewide multiresource inventory. The inventory sampled private and public lands except...

  15. Bivariate Drought Analysis Using Streamflow Reconstruction with Tree Ring Indices in the Sacramento Basin, California, USA

    Directory of Open Access Journals (Sweden)

    Jaewon Kwak

    2016-03-01

    Full Text Available Long-term streamflow data are vital for analysis of hydrological droughts. Using an artificial neural network (ANN model and nine tree-ring indices, this study reconstructed the annual streamflow of the Sacramento River for the period from 1560 to 1871. Using the reconstructed streamflow data, the copula method was used for bivariate drought analysis, deriving a hydrological drought return period plot for the Sacramento River basin. Results showed strong correlation among drought characteristics, and the drought with a 20-year return period (17.2 million acre-feet (MAF per year in the Sacramento River basin could be considered a critical level of drought for water shortages.

  16. Dissolved pesticide concentrations entering the Sacramento-San Joaquin Delta from the Sacramento and San Joaquin Rivers, California, 2012-13

    Science.gov (United States)

    Orlando, James L.; McWayne, Megan; Sanders, Corey; Hladik, Michelle

    2014-01-01

    Surface-water samples were collected from the Sacramento and San Joaquin Rivers where they enter the Sacramento–San Joaquin Delta, and analyzed by the U.S. Geological Survey for a suite of 99 current-use pesticides and pesticide degradates. Samples were collected twice per month from May 2012 through July 2013 and from May 2012 through April 2013 at the Sacramento River at Freeport, and the San Joaquin River near Vernalis, respectively. Samples were analyzed by two separate laboratory methods by using gas chromatography with mass spectrometry or liquid chromatography with tandem mass spectrometry. Method detection limits ranged from 0.9 to 10.5 nanograms per liter (ng/L). A total of 37 pesticides and degradates were detected in water samples collected during the study (18 herbicides, 11 fungicides, 7 insecticides, and 1 synergist). The most frequently detected pesticides overall were the herbicide hexazinone (detected in 100 percent of the samples); 3,4-dichloroaniline (97 percent), which is a degradate of the herbicides diuron and propanil; the fungicide azoxystrobin (83 percent); and the herbicides diuron (72 percent), simazine (66 percent), and metolachlor (64 percent). Insecticides were rarely detected during the study. Pesticide concentrations varied from below the method detection limits to 984 ng/L (hexazinone). Twenty seven pesticides and (or) degradates were detected in Sacramento River samples, and the average number of pesticides per sample was six. The most frequently detected compounds in these samples were hexazinone (detected in 100 percent of samples), 3,4-dichloroaniline (97 percent), azoxystrobin (88 percent), diuron (56 percent), and simazine (50 percent). Pesticides with the highest detected maximum concentrations in Sacramento River samples included the herbicide clomazone (670 ng/L), azoxystrobin (368 ng/L), 3,4-dichloroaniline (364 ng/L), hexazinone (130 ng/L), and propanil (110 ng/L), and all but hexazinone are primarily associated with

  17. Safety evaluation report related to Babcock and Wilcox Owners Group Plant Reassessment Program: [Final report

    International Nuclear Information System (INIS)

    1987-11-01

    After the accident of Three Mile Island, Unit 2, nuclear power plant owners made a number of improvements to their nuclear facilities. Despite these improvements, the US Nuclear Regulatory Commission (NRC) staff is concerned that the number and complexity of events at Babcock and Wilcox (B and W) nuclear plants have not decreased as expected. This concern was reinforced by the June 9, 1985 total-loss-of-feedwater event at Davis-Besse Nuclear Power Station and the December 26, 1985 overcooling transient at Rancho Seco Nuclear Generating Station. By letter dated January 24, 1986, the Executive Director for Operations (EDO) informed the Chairman of the B and W Owners Group (BWOG) that a number of recent events at B and W-designed reactors have led the NRC staff to conclude that the basic requirements for B and W reactors need to be reexamined. In its February 13, 1986 response to the EDO's letter, the BWOG committed to lead an effort to define concerns relative to reducing the frequency of reactor trips and the complexity of post-trip response in B and W plants. The BWOG submitted a description of the B and W program entitled ''Safety and Performance Improvement Program'' (BAW-1919) on May 15, 1986. Five revisions to BAW-1919 have also been submitted. The NRC staff has reviewed BAW-1919 and its revisions and presents its evaluation in this report. 2 figs., 34 tabs

  18. 77 FR 15801 - Notice of Inventory Completion: California Department of Parks and Recreation, Sacramento, CA

    Science.gov (United States)

    2012-03-16

    ...: California Department of Parks and Recreation, Sacramento, CA AGENCY: National Park Service, Interior. ACTION..., 1416 9th Street, Room 902, Sacramento, CA 95814, telephone (916) 653-8893. SUPPLEMENTARY INFORMATION... associated funerary objects were removed from the Morris Mound site (CA-SAC-199) in Sacramento County, CA...

  19. Optimization of filter loading

    International Nuclear Information System (INIS)

    Turney, J.H.; Gardiner, D.E.; Sacramento Municipal Utility District, Herald, CA)

    1985-01-01

    The introduction of 10 CFR Part 61 has created potential difficulties in the disposal of spent cartridge filters. When this report was prepared, Rancho Seco had no method of packaging and disposing of class B or C filters. This work examined methods to minimize the total operating cost of cartridge filters while maintaining them below the class A limit. It was found that by encapsulating filters in cement the filter operating costs could be minimized

  20. 78 FR 16705 - Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/Fish Screen Facility Protection...

    Science.gov (United States)

    2013-03-18

    ...-FF08RSRC00] Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/ Fish Screen Facility Protection... removal and management of invasive plant species would occur at the Riparian Sanctuary. No active... impact statement and environmental impact report (EIS/EIR) for the Llano Seco Riparian Sanctuary Unit...

  1. 77 FR 26569 - Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/Fish Screen Facility Protection...

    Science.gov (United States)

    2012-05-04

    ...-FF08RSRC00] Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/ Fish Screen Facility Protection... would occur at the Riparian Sanctuary. No active restoration of native plants would occur. Maintenance... statement and environmental impact report (EIS/EIR) for the Llano Seco Riparian Sanctuary Unit Restoration...

  2. Rumphellaones B and C, New 4,5-Seco-Caryophyllane Sesquiterpenoids from Rumphella

    Directory of Open Access Journals (Sweden)

    Hsu-Ming Chung

    2014-08-01

    Full Text Available Two new 4,5-seco-caryophyllane sesquiterpenoids, rumphellaones B (1 and C (2, which were found to possess unprecedented γ-lactone moieties, were obtained from the gorgonian coral Rumphella antipathies. The structures of 1 and 2 were elucidated by spectroscopic methods and compound 2 was found to display modest inhibitory effects on the generation of superoxide anions and the release of elastase by human neutrophils at a concentration of 10 μg/mL

  3. Sacramento, California: Solar in Action (Brochure)

    Energy Technology Data Exchange (ETDEWEB)

    2011-10-01

    This brochure provides an overview of the challenges and successes of Sacramento, CA, a 2008 Solar America City awardee, on the path toward becoming a solar-powered community. Accomplishments, case studies, key lessons learned, and local resource information are given.

  4. Trends in nutrient concentrations, loads, and yields in streams in the Sacramento, San Joaquin, and Santa Ana Basins, California, 1975-2004

    Science.gov (United States)

    Kratzer, Charles R.; Kent, Robert; Seleh, Dina K.; Knifong, Donna L.; Dileanis, Peter D.; Orlando, James L.

    2011-01-01

    A comprehensive database was assembled for the Sacramento, San Joaquin, and Santa Ana Basins in California on nutrient concentrations, flows, and point and nonpoint sources of nutrients for 1975-2004. Most of the data on nutrient concentrations (nitrate, ammonia, total nitrogen, orthophosphate, and total phosphorus) were from the U.S. Geological Survey's National Water Information System database (35.2 percent), the California Department of Water Resources (21.9 percent), the University of California at Davis (21.6 percent), and the U.S. Environmental Protection Agency's STOrage and RETrieval database (20.0 percent). Point-source discharges accounted for less than 1 percent of river flows in the Sacramento and San Joaquin Rivers, but accounted for close to 80 percent of the nonstorm flow in the Santa Ana River. Point sources accounted for 4 and 7 percent of the total nitrogen and total phosphorus loads, respectively, in the Sacramento River at Freeport for 1985-2004. Point sources accounted for 8 and 17 percent of the total nitrogen and total phosphorus loads, respectively, in the San Joaquin River near Vernalis for 1985-2004. The volume of wastewater discharged into the Santa Ana River increased almost three-fold over the study period. However, due to improvements in wastewater treatment, the total nitrogen load to the Santa Ana River from point sources in 2004 was approximately the same as in 1975 and the total phosphorus load in 2004 was less than in 1975. Nonpoint sources of nutrients estimated in this study included atmospheric deposition, fertilizer application, manure production, and tile drainage. The estimated dry deposition of nitrogen exceeded wet deposition in the Sacramento and San Joaquin Valleys and in the basin area of the Santa Ana Basin, with ratios of dry to wet deposition of 1.7, 2.8, and 9.8, respectively. Fertilizer application increased appreciably from 1987 to 2004 in all three California basins, although manure production increased in the

  5. 50 CFR 226.204 - Critical habitat for Sacramento winter-run chinook salmon.

    Science.gov (United States)

    2010-10-01

    ... 50 Wildlife and Fisheries 7 2010-10-01 2010-10-01 false Critical habitat for Sacramento winter-run chinook salmon. 226.204 Section 226.204 Wildlife and Fisheries NATIONAL MARINE FISHERIES SERVICE, NATIONAL... § 226.204 Critical habitat for Sacramento winter-run chinook salmon. The following waterways, bottom and...

  6. Occurrence and Transport of Diazinon in the Sacramento River and Selected Tributaries, California, during Two Winter Storms, January?February 2001

    Science.gov (United States)

    Dileanis, Peter D.; Brown, David L.; Knifong, Donna L.; Saleh, Dina

    2003-01-01

    Diazinon, an organophosphate insecticide, is applied as an orchard dormant spray in the Sacramento Valley during the winter months when the area receives most of its annual rainfall. During winter rainstorms that frequently follow dormant spray applications, some of the applied pesticide is transported in storm runoff to the Sacramento River and its tributaries. Diazinon is also used to control insect pests on residential and commercial properties in urban areas and is frequently detected in urban storm runoff draining into the Sacramento River system. Between January 24 and February 14, 2001, diazinon concentrations and loads were measured in the Sacramento River and selected tributaries during two winter storms that occurred after dormant spray applications were made to orchards in the Sacramento Valley. Water samples were collected at 21 sites that represented agricultural and urban inputs on a variety of scales, from small tributaries and drains representing local land use to main-stem river sites representing regional effects. Concentrations of diazinon ranged from below laboratory reporting levels to 1,380 nanograms per liter (ng/L), with a median of 55 ng/L during the first monitored storm and 26 ng/L during the second. The highest concentrations were observed in small channels draining predominantly agricultural land. About 26,000 pounds of diazinon were reported applied to agricultural land in the study area just before and during the monitoring period. About 0.2 percent of the applied insecticide appeared to be transported to the lower Sacramento River during that period. The source of about one third of the total load measured in the lower Sacramento River appears to be in the portion of the drainage basin upstream of the city of Colusa. About 12 percent of the diazinon load in the lower Sacramento River was transported from the Feather River Basin, which drains much of the mountainous eastern portions of the Sacramento River Basin. Diazinon use in the

  7. Efecto antiinflamatorio preclínico del polvo seco de Caléndula officinalis

    OpenAIRE

    Núñez Figueredo, Yanier; Montero Alarcón, Claudia; Agüero Fernández, Sara; Muñoz Cernuda, Adriana

    2007-01-01

    Para demostrar la actividad antiinflamatoria del polvo seco Caléndula officinalis secado por atomización se emplearon dosis de 50, 150 y 450 mg/Kg y se evaluó el efecto sobre la inflamación aguda provocada por carragenina, dextrán, histamina y serotonina y granuloma inducido por discos de algodón en ratas y edema auricular inducido por aceite de crotón en ratones. El polvo seco mostró efecto inhibitorio sobre los diferentes modelos empleados sin afectar el peso del timo y las glándulas suprar...

  8. Consumo de frutos secos y aceites vegetales en personas con diabetes mellitus tipo 1

    OpenAIRE

    Ferrer-García, Juan Carlos; Granell Vidal, Lina; Muñoz Izquierdo, Amparo; Sánchez Juan, Carlos

    2015-01-01

    Introducción: estudios recientes han demostrado los beneficios cardiovasculares de la dieta mediterránea enriquecida con aceite de oliva y frutos secos. Las personas con diabetes, que tienen un mayor riesgo de complicaciones cardiovasculares, podrían beneficiarse en gran medida de seguir ese tipo de patrón alimentario. Objetivos: análisis de la ingesta de grasas vegetales procedentes de frutos secos y aceites vegetales en pacientes con diabetes mellitus tipo 1 (DM1). Métodos: estudio transver...

  9. RadNet Air Data From Sacramento, CA

    Science.gov (United States)

    This page presents radiation air monitoring and air filter analysis data for Sacramento, CA from EPA's RadNet system. RadNet is a nationwide network of monitoring stations that measure radiation in air, drinking water and precipitation.

  10. Exploring SWOT discharge algorithm accuracy on the Sacramento River

    Science.gov (United States)

    Durand, M. T.; Yoon, Y.; Rodriguez, E.; Minear, J. T.; Andreadis, K.; Pavelsky, T. M.; Alsdorf, D. E.; Smith, L. C.; Bales, J. D.

    2012-12-01

    Scheduled for launch in 2019, the Surface Water and Ocean Topography (SWOT) satellite mission will utilize a Ka-band radar interferometer to measure river heights, widths, and slopes, globally, as well as characterize storage change in lakes and ocean surface dynamics with a spatial resolution ranging from 10 - 70 m, with temporal revisits on the order of a week. A discharge algorithm has been formulated to solve the inverse problem of characterizing river bathymetry and the roughness coefficient from SWOT observations. The algorithm uses a Bayesian Markov Chain estimation approach, treats rivers as sets of interconnected reaches (typically 5 km - 10 km in length), and produces best estimates of river bathymetry, roughness coefficient, and discharge, given SWOT observables. AirSWOT (the airborne version of SWOT) consists of a radar interferometer similar to SWOT, but mounted aboard an aircraft. AirSWOT spatial resolution will range from 1 - 35 m. In early 2013, AirSWOT will perform several flights over the Sacramento River, capturing river height, width, and slope at several different flow conditions. The Sacramento River presents an excellent target given that the river includes some stretches heavily affected by management (diversions, bypasses, etc.). AirSWOT measurements will be used to validate SWOT observation performance, but are also a unique opportunity for testing and demonstrating the capabilities and limitations of the discharge algorithm. This study uses HEC-RAS simulations of the Sacramento River to first, characterize expected discharge algorithm accuracy on the Sacramento River, and second to explore the required AirSWOT measurements needed to perform a successful inverse with the discharge algorithm. We focus on several specific research questions affecting algorithm performance: 1) To what extent do lateral inflows confound algorithm performance? We examine the ~100 km stretch of river from Colusa, CA to the Yolo Bypass, and investigate how the

  11. 75 FR 40762 - Revisions to the California State Implementation Plan, Sacramento Metropolitan Air Quality...

    Science.gov (United States)

    2010-07-14

    ... the California State Implementation Plan, Sacramento Metropolitan Air Quality Management District and South Coast Air Quality Management District AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed rule. SUMMARY: EPA is proposing to approve revisions to the Sacramento Metropolitan Air Quality...

  12. Colônia do Sacramento: a situação na fronteira platina no século XVIII

    Directory of Open Access Journals (Sweden)

    Fabrício Pereira Prado

    2003-07-01

    Full Text Available A Colônia do Sacramento, no atual Uruguai, na primeira metade do século XVIII, constituiu uma cidade de pródigo comércio na região platina. Inseridos tanto nas rotas comerciais e sociais portuguesas quanto nas castelhanas, os habitantes de Sacramento materializavam uma fronteira múltipla, onde coexistiam espanhóis, portugueses e diferentes grupos indígenas. O presente estudo analisa os vínculos sociais e comerciais existentes entre os habitantes de Sacramento e os de Buenos Aires. No interior do espaço platino as redes sociais estabelecidas através do rio da Prata, ligando Sacramento e Buenos Aires, eram vias de acúmulo de prestígio, poder e riqueza em uma sociedade de antigo regime.The Sacramento Colony, currently Uruguayan territory, in the first half of the XVIII century, was a city with great commerce on the River Plate Region. Placed in both Portuguese and Spanish social and commercial routes, the Sacramento habitants formed a multiple frontier where Spanish, Portuguese and different indigenous groups coexisted. The present study analyses the social and commercial links that existed between the Sacramento and Buenos Aires inhabitants. In the River Plate region, the social networks developed connecting Sacramento and Buenos Ayers were gateways to social status, power and wealth in an old regime society.

  13. 78 FR 10589 - Revision of Air Quality Implementation Plan; California; Sacramento Metropolitan Air Quality...

    Science.gov (United States)

    2013-02-14

    ... Quality Implementation Plan; California; Sacramento Metropolitan Air Quality Management District... Sacramento Metropolitan Air Quality Management District (SMAQMD or District) portion of the California State... sources within the areas covered by the plan as necessary to assure that the National Ambient Air Quality...

  14. Radionuclide Site Survey Report Sacramento, California (RN-70)

    National Research Council Canada - National Science Library

    Walker, Frank

    1999-01-01

    The purpose of this report is to validate that the Sacramento, CA, site will fulfill treaty requirements as set forth by the Preparatory Commission for the Comprehensive Test Ban Treaty Organization...

  15. Copper, cadmium, and zinc concentrations in aquatic food chains from the Upper Sacramento River (California) and selected tributaries

    Science.gov (United States)

    Saiki, M.K.; Castleberry, D. T.; May, T. W.; Martin, B.A.; Bullard, F. N.

    1995-01-01

    Metals enter the Upper Sacramento River above Redding, California, primarily through Spring Creek, a tributary that receives acid-mine drainage from a US EPA Superfund site known locally as Iron Mountain Mine. Waterweed (Elodea canadensis) and aquatic insects (midge larvae, Chironomidae; and mayfly nymphs, Ephemeroptera) from the Sacramento River downstream from Spring Creek contained much higher concentrations of copper (Cu), cadmium (Cd), and zinc (Zn) than did similar taxa from nearby reference tributaries not exposed to acid-mine drainage. Aquatic insects from the Sacramento River contained especially high maximum concentrations of Cu (200 mg/kg dry weight in midge larvae), Cd (23 mg/kg dry weight in mayfly nymphs), and Zn (1,700 mg/kg dry weight in mayfly nymphs). Although not always statistically significant, whole-body concentrations of Cu, Cd, and Zn in fishes (threespine stickleback, Gasterosteus aculeatus; Sacramento sucker, Catostomus occidentalis; Sacramento squawfish, Ptychocheilus grandis; and chinook salmon, Oncorhynchus tshawytasch) from the Sacramento River were generally higher than in fishes from the reference tributaries.

  16. Isolation of biosurfactant-producing bacteria from the Rancho La Brea Tar Pits.

    Science.gov (United States)

    Belcher, Richard W; Huynh, Kelvin V; Hoang, Timothy V; Crowley, David E

    2012-12-01

    This research was conducted to identify culturable surfactant-producing bacterial species that inhabit the 40,000-year-old natural asphalt seep at the Rancho La Brea Tar Pits in Los Angeles, CA. Using phenanthrene, monocyclic aromatic hydrocarbons, and tryptic soy broth as growth substrates, culturable bacteria from the tar pits yielded ten isolates, of which three species of gamma-proteobacteria produced biosurfactants that accumulated in spent culture medium. Partially purified biosurfactants produced by these strains lowered the surface tension of water from 70 to 35-55 mN/m and two of the biosurfactants produced 'dark halos' with the atomized oil assay, a phenomenon previously observed only with synthetic surfactants. Key findings include the isolation of culturable biosurfactant-producing bacteria that comprise a relatively small fraction of the petroleum-degrading community in the asphalt.

  17. Digital control of research reactors

    International Nuclear Information System (INIS)

    Crump, J.C. III.; Richards, W.J.; Heidel, C.C.

    1991-01-01

    Research reactors provide an important service for the nuclear industry. Developments and innovations used for research reactors can be later applied to larger power reactors. Their relatively inexpensive cost allows research reactors to be an excellent testing ground for the reactors of tomorrow. One area of current interest is digital control of research reactor systems. Digital control systems offer the benefits of implementation and superior system response over their analog counterparts. At McClellan Air Force Base in Sacramento, California, the Stationary Neutron Radiography System (SNRS) uses a 1,000-kW TRIGA reactor for neutron radiography and other nuclear research missions. The neutron radiography beams generated by the reactor are used to detect corrosion in aircraft structures. While the use of the reactor to inspect intact F-111 wings is in itself noteworthy, there is another area in which the facility has applied new technology: the instrumentation and control system (ICS). The ICS developed by General Atomics (GA) contains several new and significant items: (a) the ability to servocontrol on three rods, (b) the ability to produce a square wave, and (c) the use of a software configurator to tune parameters affected by the actual reactor core dynamics. These items will probably be present in most, if not all, future research reactors. They were developed with increased control and overall usefulness of the reactor in mind

  18. Pesticides in surface water measured at select sites in the Sacramento River basin, California, 1996-1998

    Science.gov (United States)

    Domagalski, Joseph L.

    2000-01-01

    Pesticides were measured in one urban stream, one agricultural stream, one site on the Sacramento River, and one large flood control channel over a period of 18 months during 1996-1998. All sites were located within the Sacramento River Basin of California. Measurements were made on 83 pesticides or pesticide transformation products by either gas chromatography/mass spectrometry or by high performance liquid chromatography with ultraviolet light spectrometry. Some pesticides were detected frequently at the agricultural stream and downstream in the Sacramento River and at the flood control channel of the Sacramento River. These were pesticides related to rice farming (molinate, carbofuran, thiobencarb, and bentazon); herbicides used both agriculturally or for roadside maintenance (diuron, simazine, and metolachlor); or insecticides used on orchards and row corps (diazinon and chlorpyrifos). No pesticide concen-trations above enforceable water quality criteria were measured at either the agricultural site or the Sacramento River sites. In contrast to the agricul-tural site, insecticides used for household, lawn, or garden maintenance were the most frequently detected pesticides at the urban site. Diazinon, an organophosphate insecticide, exceeded recom-mended criteria for the protection of aquatic life, and the diazinon levels were frequently above known toxic levels for certain zooplankton species at the urban site. Because of the low discharge of the urban stream, pesticide concentrations were greatly diluted upon mixing with Sacramento River water.

  19. McClellan Nuclear Radiation Center (MNRC) TRIGA reactor: Four years of operations

    International Nuclear Information System (INIS)

    Heidel, C.C.; Richards, W.J.

    1994-01-01

    McClellan Air Force Base, at Sacramento, California, is headquarters for the Sacramento Air Force Logistics Center (SM-ALC). McClellan Air Force Base provides extensive inspection and maintenance capabilities for the F-111, F-1 5, and other military aircraft. Criticality of the MNRC TRIGA reactor was obtained on January 20, 1990 with 63 standard TRIGA fuel elements, three fuel-followed control rods and one air-followed control rod. Presently there are 93 fuel elements in the reactor core. The reactor can be operated at 1 MW steady state power, producing pulses up to three dollars worth of reactivity addition, and can be square waved up to 1 MW. The reactor core contains a circular grid plate and a graphite reflector assembly surrounding the core. Four tangential beam ports installed in the reflector assembly provide a thermal neutron flux to four radiography bays. The reactor tank is twenty-four (24) feet deep, seven and one-half (7.5) feet in diameter, and has a protrusion in the upper portion of the reactor tank. This protrusion is scheduled for use as a neutron thermal collimator in the future. Besides the neutron radiography capabilities, the reactor contains a pneumatic rabbit system, a central thimble, an in-core irradiation facility, and three additional cutouts that provide locations for additional irradiation facilities. The central thimble can be removed along with the B-ring locations of the upper portion of the grid plate to provide an additional and larger in-core irradiation facility. A new upper grid plate has been manufactured to expand one triangular cutout so that larger experiments can be inserted directly into the reactor core. Some operational problems experienced during the first four years of operations are the timeout of the CSC and DAC watchdogs, deterioration of the heat exchanger gaskets, and loss of thermocouples in the instrumented fuel elements. (author)

  20. 77 FR 19687 - Notice of Inventory Completion: California Department of Parks and Recreation, Sacramento, CA

    Science.gov (United States)

    2012-04-02

    ...: California Department of Parks and Recreation, Sacramento, CA AGENCY: National Park Service, Interior. ACTION..., 1416 9th Street, Room 902, Sacramento, CA 95814, telephone (916) 653-8893. SUPPLEMENTARY INFORMATION... associated funerary objects were removed from ten sites located in northeastern San Diego County, CA. This...

  1. 77 FR 76451 - Designation for the West Sacramento, CA; Frankfort, IN; and Richmond, VA Areas.

    Science.gov (United States)

    2012-12-28

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

  2. Leafcutter bee nests and pupae from the Rancho La Brea Tar Pits of southern California: Implications for understanding the paleoenvironment of the Late Pleistocene

    Science.gov (United States)

    The Rancho La Brea Tar Pits is the world’s richest and most important Late Pleistocene fossil locality and best renowned for numerous fossil mammals and birds excavated over the past century. Less researched are insects, even though these specimens frequently serve as the most valuable paleoenvironm...

  3. Distribution and geochemistry of selected trace elements in the Sacramento River near Keswick Reservoir

    Science.gov (United States)

    Antweiler, Ronald C.; Taylor, Howard E.; Alpers, Charles N.

    2012-01-01

    The effect of heavy metals from the Iron Mountain Mines (IMM) Superfund site on the upper Sacramento River is examined using data from water and bed sediment samples collected during 1996-97. Relative to surrounding waters, aluminum, cadmium, cobalt, copper, iron, lead, manganese, thallium, zinc and the rare-earth elements (REE) were all present in high concentrations in effluent from Spring Creek Reservoir (SCR), which enters into the Sacramento River in the Spring Creek Arm of Keswick Reservoir. SCR was constructed in part to regulate the flow of acidic, metal-rich waters draining the IMM Superfund site. Although virtually all of these metals exist in SCR in the dissolved form, upon entering Keswick Reservoir they at least partially converted via precipitation and/or adsorption to the particulate phase. In spite of this, few of the metals settled out; instead the vast majority was transported colloidally down the Sacramento River at least to Bend Bridge, 67. km from Keswick Dam.The geochemical influence of IMM on the upper Sacramento River was variable, chiefly dependent on the flow of Spring Creek. Although the average flow of the Sacramento River at Keswick Dam is 250m 3/s (cubic meters per second), even flows as low as 0.3m 3/s from Spring Creek were sufficient to account for more than 15% of the metals loading at Bend Bridge, and these proportions increased with increasing Spring Creek flow.The dissolved proportion of the total bioavailable load was dependent on the element but steadily decreased for all metals, from near 100% in Spring Creek to values (for some elements) of less than 1% at Bend Bridge; failure to account for the suspended sediment load in assessments of the effect of metals transport in the Sacramento River can result in estimates which are low by as much as a factor of 100. ?? 2012.

  4. Quaternary geologic map of the north-central part of the Salinas River Valley and Arroyo Seco, Monterey County, California

    Science.gov (United States)

    Taylor, Emily M.; Sweetkind, Donald S.

    2014-01-01

    Arroyo Seco, a perennial drainage in the central Coast Range of California, records a sequence of strath terraces. These terraces preserve an erosional and depositional history, controlled by both climate change and regional tectonics. These deposits have been mapped and correlated on the basis of field investigations, digital terrain analysis, stream gradient profiles, evaluation of published regional soil maps, and satellite imagery. Seven of the strath terraces and associated alluvial fans have been dated by optically stimulated luminescence (OSL) or infrared stimulated luminescence (IRSL). The OSL and IRSL dates on seven of the strath terraces and associated alluvial fans in Arroyo Seco are approximately >120 ka, >65 ka, 51–46 ka, 36–35 ka, 9 ka, and 2–1 ka. These dates generally fall within the range of ages reported from many well-dated marine terraces on the California coast that are formed during sea-level high stands. Tectonic movements, consistently upward, result in a constantly and slowly emerging coastline, however, the regional effects of climate change and resulting eustatic sea-level rises are interpreted as the driving mechanism for erosion and aggradation in Arroyo Seco.

  5. Actualización clínica en OJO seco para el médico no oftalmólogo

    Directory of Open Access Journals (Sweden)

    Dr. P. Arturo Kantor

    2010-11-01

    Full Text Available La presente revisión de tema ojo seco está orientada a médicos no oftalmólogos. Se realiza un repaso de la anatomía del sistema lagrimal y fisiología básica de la película lagrimal. Se define el concepto de ojo seco, su importancia epidemiológica y su sintomatología. Se realiza un detallado análisis de la clasificación etiológica definiendo las diferencias entre hipolacrimea asociada o no a síndrome de Sjögren y ojo seco evaporativo de causa intrínseca y extríniseca, con énfasis en los mecanismos fisiopatológicos subyacentes. Se entrega una visión que da cuenta de la complejidad, envergadura y condición multifactorial de este problema de salud visual y se hace énfasis en la necesidad de identificar de manera integral el tipo de ojo seco para poder instalar un tratamiento basado en la corrección del mecanismo subyacente y no a través de aproximación sintomática de la terapia.

  6. 77 FR 15389 - Notice of Inventory Completion: California Department of Parks and Recreation, Sacramento, CA

    Science.gov (United States)

    2012-03-15

    ...: California Department of Parks and Recreation, Sacramento, CA AGENCY: National Park Service, Interior. ACTION..., 1416 9th Street, Room 902, Sacramento, CA 95814, telephone (916) 653-8893. SUPPLEMENTARY INFORMATION... associated funerary objects were removed from the Cole Creek site (CA-LAK-425), Lake County, CA. This notice...

  7. 77 FR 47789 - Drawbridge Operation Regulation; Sacramento River, CA

    Science.gov (United States)

    2012-08-10

    ...-Club Yacht Association, the Recreational Boaters of California, the Capital City Yacht Club, the Sacramento Yacht Club, River View Yacht Club and Hornblower Cruises. D. Discussion of Proposed Rule Under the...

  8. 77 FR 19690 - Notice of Inventory Completion: California Department of Parks and Recreation, Sacramento, CA

    Science.gov (United States)

    2012-04-02

    ...: California Department of Parks and Recreation, Sacramento, CA AGENCY: National Park Service, Interior. ACTION... Department of Parks and Recreation, 1416 9th Street, Room 902, Sacramento, CA 95814, telephone (916) 653-8893... located in San Diego County, CA. This notice is published as part of the National Park Service's...

  9. 77 FR 19689 - Notice of Inventory Completion: California Department of Parks and Recreation, Sacramento, CA

    Science.gov (United States)

    2012-04-02

    ...: California Department of Parks and Recreation, Sacramento, CA AGENCY: National Park Service, Interior. ACTION... Department of Parks and Recreation, 1416 9th Street, Room 902, Sacramento, CA 95814, telephone (916) 653-8893... located in San Diego County, CA. This notice is published as part of the National Park Service's...

  10. Utilización de lodo seco de depuradora de aguas residuales como adición en adoquines de hormigón prefabricado

    OpenAIRE

    Yagüe, A.; Valls, S.; Vázquez, E.; Kuchinow, V.

    2002-01-01

    El estudio ha consistido en la utilización de lodo seco de origen biológico de la depuradora de aguas residuales de Sabadell (Riu Sec), como adición en la preparación de adoquines de hormigón prefabricado. Después de caracterizar los lodos y el proceso de fabricación de los adoquines que utilizaremos, definimos las condiciones de adición de los lodos en esta fabricación. Se prepararon muestras de referencia, sin adición, y muestras con el 2 % de lodo seco sobrepeso de cemento. Se determina...

  11. D-seco-Vitamin D analogs having reversed configurations at C-13 and C-14: Synthesis, docking studies and biological evaluation.

    Science.gov (United States)

    Szybinski, Marcin; Sokolowska, Katarzyna; Sicinski, Rafal R; Plum, Lori A; DeLuca, Hector F

    2017-10-01

    Prompted by results of molecular modeling performed on the seco-d-ring-vitamins D, we turned our attention to such analogs, having reversed configurations at C-13 and C-14, as the next goals of our studies on the structure-activity relationship for vitamin D compounds. First, we developed an efficient total synthesis of the "upper" C/seco-d-ring fragment with a 7-carbon side chain. Then, we coupled it with A-ring fragments using Sonogashira or Wittig-Horner protocol, providing the targeted D-seco analogs of 1α,25-dihydroxyvitamin D 3 and 1α,25-dihydroxy-19-norvitamin D 3 possessing a vinyl substituent at C-14 and a double bond between C-17 and C-20. The affinities of the synthesized vitamin D analogs to the full-length recombinant rat VDR were examined, as well as their differentiating and transcriptional activities. In these in vitro tests, they were significantly less active compared to 1α,25-(OH) 2 D 3 . Moreover, it was established that the analogs tested in vivo in rats showed no calcemic potency. Copyright © 2016 Elsevier Ltd. All rights reserved.

  12. Abundancia, diversidad y categoría ecológica de los peces en estero damas y estero palo seco, Costa Rica

    Directory of Open Access Journals (Sweden)

    Hubert Araya

    2016-03-01

    Full Text Available Se trabajó de junio de 1986 a febrero de 1987 en una estación de muestreo en el estero Palo Seco y en dos en el estero Damas (Damas y San Bosco, Pacífico Central, Costa Rica. La temperatura del agua no presentó diferencias significativas entre las estaciones Damas y San Bosco, pero sí entre Damas-Palo Seco y San Bosco-Palo Seco. La salinidad varió significativamente entre las tres estaciones y el pH no mostró diferencias significativas. Se recolectaron representantes de 25 familias, 39 géneros y 54 especies. De las especies, 18 comparten los tres sitios de muestreo, siete se hallaron únicamente en Palo Seco, cinco en Damas y seis en San Bosco. De las especies recolectadas, el 7,41% es compartido entre Palo Seco y Damas; el 3,70% entre Palo Seco y San Bosco y el 22,22% entre Damas y San Bosco. El análisis de similitud determinó que las estaciones Damas y San Bosco comparten un 41,40% de las especies; mientras que Palo Seco solamente presento un 9,9% de especies comunes con el grupo Damas-San Bosco. La mayoría de las especies encontradas fueron de origen marino que utilizan estos dos esteros como área de crianza (42,59% y alimentación (40,74%; mientras que las de agua dulce, estuarinas y visitantes ocasionales están poco representadas. La mayor diversidad se encontró en San Bosco y se detectaron diferencias estadísticamente significativas en los valores de H' entre las estaciones. La mayor similitud de especies se presentó entre las estaciones Damas y San Bosco, lo que sugiere que estas áreas están bajo una mayor influencia de aguas continentales; lo que propicia que los peces estén más ampliamente distribuidos. Se deduce que la ictiofauna de los esteros estudiados es transitoria en los sitios de muestreo y que la misma se distribuye heterogéneamente.

  13. Effects of seco-steroids purified from Physalis angulata L., Solanaceae, on the viability of Leishmania sp Efeitos de seco-esteróides purificados de Physalis angulata L., Solanaceae na viabilidade de Leishmania sp

    Directory of Open Access Journals (Sweden)

    Elisalva T. Guimarães

    2010-12-01

    Full Text Available Physalis angulata L., Solanaceae, is an annual herb commonly used in popular medicine in many tropical and subtropical countries. P. angulata extracts contain a variety of substances, but little is known about their pharmacological activities. In this work we investigated the in vitro antileishmanial activity of seco-steroids (physalins purified from P. angulata. Addition of physalins B, F, and G caused a concentration-dependent inhibition in the growth of L. amazonensis promastigotes, being the IC50 values were 6.8, 1.4, and 9.2 μM, respectively. Physalin D was less active and had an IC50 value of 30.5 μM. Physalins were also active in cultures of other Leishmania species (L. major, L. braziliensis, and L. chagasi. Our results demonstrate the potent antileishmanial activity of physalins in cultures of Leishmania species of the New and Old Worlds and suggest the therapeutic potential of these seco-steroids in leishmaniasis.Physalis angulata L., Solanaceae, é uma erva anual utilizada na medicina popular em muitos países tropicais e subtropicais. Apesar dos extratos da P. angulata apresentarem uma grande variedade de substâncias, pouco é conhecido sobre a sua atividade farmacológica. Neste trabalho foi investigado a atividade antileishmania in vitro de seco-esteroides (fisalinas purificados da P. angulata. O tratamento com as fisalinas B, F e G causou uma inibição concentração-dependente do crescimento de promastigotas de Leishmania amazonensis em cultura axênica, com valores de IC50 de 6,8, 1,4, e 9,2 μM respectivamente. A fisalina D foi menos ativa, com valores de IC50 de 30,5 μM. Foi também observada uma atividade leishmanicida em culturas de outras espécies de Leishmania (L. major, L. braziliensis e L. chagasi. Nossos resultados demonstram que as fisalinas inibem o crescimento dos promastigotas com o tratamento de espécies de Leishmania do Velho e do Novo Mundos e sugerem o potencial terapêutico destas moléculas na

  14. 76 FR 9709 - Water Quality Challenges in the San Francisco Bay/Sacramento-San Joaquin Delta Estuary

    Science.gov (United States)

    2011-02-22

    ... Water Quality Challenges in the San Francisco Bay/Sacramento-San Joaquin Delta Estuary AGENCY... the San Francisco Bay/ Sacramento-San Joaquin Delta Estuary (Bay Delta Estuary) in California. EPA is... programs to address recent significant declines in multiple aquatic species in the Bay Delta Estuary. EPA...

  15. COMPOSICIÓN DEL ENSAMBLE DE INSECTOS DEL DOSEL DE BOSQUES SUBTROPICALES SECOS DEL CHACO SEMIÁRIDO, ARGENTINA

    OpenAIRE

    Liliana Diodato; Andrea Fuster

    2016-01-01

    El dosel arbóreo constituye un complejo hábitat con gran diversidad de insectos. Los estudios sobre insectos del dosel están mayormente concentrados en bosques húmedos tropicales y son escasos en bosques secos subtropicales. El propósito de este trabajo fue caracterizar la entomofauna del dosel de bosques secos subtropicales, analizando su diversidad regional y localmente. Para ello se muestrearon cinco sitios localizados en la región fitogeográfica del Chaco Semiárido Argentino. Las recolecc...

  16. Biology, History, Status and Conservation of Sacramento Perch, Archoplites interruptus

    Directory of Open Access Journals (Sweden)

    Patrick K Crain

    2011-04-01

    Full Text Available This paper is a review of the biology of Sacramento perch (Archoplites interruptus based mainly on recent studies of their distribution, ecology, physiology, and genetics. The Sacramento perch is the only member of the family Centrarchidae that is endemic to California. It is most closely related to the rock basses (Ambloplites spp. and is thought to have split from its eastern cousins during the Middle Miocene Period (15.5 to 5.2 million years ago, MYA. Their native range includes the Central Valley, Pajaro and Salinas rivers, tributaries to the San Francisco Estuary (e.g., Alameda Creek, and Clear Lake (Lake County. Today, they are most likely extirpated from all of their native range. They are known to persist in 28 waters outside their native range: 17 in California, nine in Nevada, and one each in Utah and Colorado. Disappearance from their native range coincided with massive changes to aquatic habitats in the Central Valley and with the introduction of alien species, including other centrarchids. Unfortunately, many populations established outside their native range have also disappeared and are continuing to do so.

  17. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported.

  18. Reactor BR2

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported

  19. Environmental Scan of the Greater Sacramento Area, 1999.

    Science.gov (United States)

    Los Rios Community Coll. District, Sacramento, CA. Office of Planning and Research.

    This report provides a comprehensive look at the external environment impacting Los Rios Community College District (LRCCD) (California). It summarizes the social, economic, and political changes at the state and national levels, in general, and in the Sacramento-Yolo Consolidated Metropolitan Statistical Area (CMSA) served by LRCCD, more…

  20. "2por km2" chozos, estructuras y corrales de piedra en seco en la superficie del término de Tebar, Cuenca

    OpenAIRE

    Ruiz Checa, José Ramón; Cristini, Valentina

    2011-01-01

    [ES] Tanto en la península Ibérica (Maestrazgo... Islas Baleares...), como en Europa (Provenza... Liguria...) aparecen «paisajes construidos» con piedra en seco. Se trata realmente de parajes antropizados prácticamente en toda su totalidad, resultado de un afán milenario de domesticación del territorio, a través de estructuras hidráulicas, pistas, cañadas...caminos, bancales, construcciones o recintos. El caso de Tébar, un municipio a 94 km al sur oeste de Cuenca, e...

  1. Identification and functional characterization of a flax UDP-glycosyltransferase glucosylating secoisolariciresinol (SECO) into secoisolariciresinol monoglucoside (SMG) and diglucoside (SDG).

    Science.gov (United States)

    Ghose, Kaushik; Selvaraj, Kumarakurubaran; McCallum, Jason; Kirby, Chris W; Sweeney-Nixon, Marva; Cloutier, Sylvie J; Deyholos, Michael; Datla, Raju; Fofana, Bourlaye

    2014-03-28

    Lignans are a class of diphenolic nonsteroidal phytoestrogens often found glycosylated in planta. Flax seeds are a rich source of secoisolariciresinol diglucoside (SDG) lignans. Glycosylation is a process by which a glycosyl group is covalently attached to an aglycone substrate and is catalyzed by uridine diphosphate glycosyltransferases (UGTs). Until now, very little information was available on UGT genes that may play a role in flax SDG biosynthesis. Here we report on the identification, structural and functional characterization of 5 putative UGTs potentially involved in secoisolariciresinol (SECO) glucosylation in flax. Five UGT genes belonging to the glycosyltransferases' family 1 (EC 2.4.x.y) were cloned and characterized. They fall under four UGT families corresponding to five sub-families referred to as UGT74S1, UGT74T1, UGT89B3, UGT94H1, UGT712B1 that all display the characteristic plant secondary product glycosyltransferase (PSPG) conserved motif. However, diversity was observed within this 44 amino acid sequence, especially in the two peptide sequences WAPQV and HCGWNS known to play a key role in the recognition and binding of diverse aglycone substrates and in the sugar donor specificity. In developing flax seeds, UGT74S1 and UGT94H1 showed a coordinated gene expression with that of pinoresinol-lariciresinol reductase (PLR) and their gene expression patterns correlated with SDG biosynthesis. Enzyme assays of the five heterologously expressed UGTs identified UGT74S1 as the only one using SECO as substrate, forming SECO monoglucoside (SMG) and then SDG in a sequential manner. We have cloned and characterized five flax UGTs and provided evidence that UGT74S1 uses SECO as substrate to form SDG in vitro. This study allowed us to propose a model for the missing step in SDG lignan biosynthesis.

  2. Sequence-specific DNA alkylation targeting for Kras codon 13 mutation by pyrrole-imidazole polyamide seco-CBI conjugates.

    Science.gov (United States)

    Taylor, Rhys Dylan; Asamitsu, Sefan; Takenaka, Tomohiro; Yamamoto, Makoto; Hashiya, Kaori; Kawamoto, Yusuke; Bando, Toshikazu; Nagase, Hiroki; Sugiyama, Hiroshi

    2014-01-27

    Hairpin N-methylpyrrole-N-methylimidazole polyamide seco-CBI conjugates 2-6 were designed for synthesis by Fmoc solid-phase synthesis, and their DNA-alkylating activities against the Kras codon 13 mutation were compared by high-resolution denaturing gel electrophoresis with 225 base pair (bp) DNA fragments. Conjugate 5 had high reactivity towards the Kras codon 13 mutation site, with alkylation occurring at the A of the sequence 5'-ACGTCACCA-3' (site 2), including minor 1 bp-mismatch alkylation against wild type 5'-ACGCCACCA-3' (site 3). Conjugate 6, which differs from conjugate 5 by exchanging one Py unit with a β unit, showed high selectivity but only weakly alkylated the A of 5'-ACGTCACCA-3' (site 2). The hairpin polyamide seco-CBI conjugate 5 thus alkylates according to Dervan's pairing rule with the pairing recognition which β/β pair targets T-A and A-T pairs. SPR and a computer-minimized model suggest that 5 binds to the target sequence with high affinity in a hairpin conformation, allowing for efficient DNA alkylation. Copyright © 2014 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  3. Selected trace elements in the Sacramento River, California: Occurrence and distribution

    Science.gov (United States)

    Taylor, Howard E.; Antweiler, Ronald C.; Roth, David A.; Dileanis, Peter D.; Alpers, Charles N.

    2012-01-01

    The impact of trace elements from the Iron Mountain Superfund site on the Sacramento River and selected tributaries is examined. The concentration and distribution of many trace elements—including aluminum, arsenic, boron, barium, beryllium, bismuth, cadmium, cerium, cobalt, chromium, cesium, copper, dysprosium, erbium, europium, iron, gadolinium, holmium, potassium, lanthanum, lithium, lutetium, manganese, molybdenum, neodymium, nickel, lead, praseodymium, rubidium, rhenium, antimony, selenium, samarium, strontium, terbium, thallium, thulium, uranium, vanadium, tungsten, yttrium, ytterbium, zinc, and zirconium—were measured using a combination of inductively coupled plasma-mass spectrometry and inductively coupled plasma-atomic emission spectrometry. Samples were collected using ultraclean techniques at selected sites in tributaries and the Sacramento River from below Shasta Dam to Freeport, California, at six separate time periods from mid-1996 to mid-1997. Trace-element concentrations in dissolved (ultrafiltered [0.005-μm pore size]) and colloidal material, isolated at each site from large volume samples, are reported. For example, dissolved Zn ranged from 900 μg/L at Spring Creek (Iron Mountain acid mine drainage into Keswick Reservoir) to 0.65 μg/L at the Freeport site on the Sacramento River. Zn associated with colloidal material ranged from 4.3 μg/L (colloid-equivalent concentration) in Spring Creek to 21.8 μg/L at the Colusa site on the Sacramento River. Virtually all of the trace elements exist in Spring Creek in the dissolved form. On entering Keswick Reservoir, the metals are at least partially converted by precipitation or adsorption to the particulate phase. Despite this observation, few of the elements are removed by settling; instead the majority is transported, associated with colloids, downriver, at least to the Bend Bridge site, which is 67 km from Keswick Dam. Most trace elements are strongly associated with the colloid phase going

  4. A New Data Acquisition Portal for the Sacramento River Settlement Contractors

    Science.gov (United States)

    Narlesky, P. E., C. A.; Williams, P. E., A. M.

    2017-12-01

    In 1964, the United States Bureau of Reclamation (Reclamation) executed settlement contracts with the Sacramento River Settlement Contractors (SRSC), entities which hold water rights along the Sacramento River with area of origin protection or that are senior to Reclamation's water rights for Shasta Reservoir. Shasta is the cornerstone of the federal Central Valley Project (CVP), one of the nation's largest multi-purpose water conservation programs. In order to optimize CVP operations for multiple beneficial uses including water supply, fisheries, water quality, and waterfowl habitat, the SRSC voluntarily agreed to adaptively manage diversions throughout the year in close coordination with Reclamation. MBK Engineers assists the SRSC throughout this process by collecting, organizing, compiling, and distributing diversion data to Reclamation and others involved in operational decisions related to Shasta Reservoir and the CVP. To improve and expand participation in diversions reporting, we have developed the SRSC Web Portal, which launches a data-entry dashboard for members of the SRSC to facilitate recording and transmittal of both predicted and observed monthly and daily flow diversion data. This cloud-hosted system leverages a combination of Javascript interactive visualization libraries with a database-backed Python web framework to present streamlined data-entry forms and valuable SRSC program summary illustrations. SRSC program totals, which can now be aggregated through queries to the web-app's database backend, are used by Reclamation, SRSC, fish agencies, and others to inform operational decisions. By submitting diversion schedules and tracking actual diversions through the portal, contractors will also be directly contributing to the development of a richer and more consistently-formatted historical record for demand hydrology in the Sacramento River Watershed; this may be useful in future water supply studies. Adoption of this technology will foster an

  5. Exploring the roles of temperature and NOx on ozone production in the Sacramento urban plume

    Science.gov (United States)

    Lafranchi, B. W.; Cohen, R. C.

    2009-12-01

    We investigate the role of temperature and NOx (NOx = NO+NO2) on ozone (O3) production in the Sacramento urban plume over a stretch of seven years (2001-2007) using data collected at UC Blodgett Forest Research Station (a forested site in the Sierra Nevadas about 80 km downwind of Sacramento, CA) and at a series of California Air Resources Board (CARB) sites along the Sacramento-Blodgett transect. The consistent daytime wind patterns between the Central Valley of California and the foothills of the Sierra Nevada mountains permits the assumption of plume transport from downtown Sacramento, over the CARB monitoring sites in the eastern suburbs, and past the Blodgett Forest research site. While NOx emissions are limited primarily to the urban and suburban regions of the transect, biogenic volatile organic compound (VOC) emissions are significant throughout the transect, thus there is a fast transition from VOC-limited to NOx-limited as the plume travels away from the urban center, and we have the opportunity to analyze the differences in ozone production across these two chemical regimes. For this analysis, the Sacramento-Blodgett transect is separated into three segments: urban, suburban, and rural, defined by the locations of selected monitoring sites. Ozone concentrations across each segment are controlled by chemical production (Pchem) and loss (Lchem), deposition to surfaces (Ldep), and mixing with background air (Lmix). At an assumed deposition rate, mixing rate, and background O3 concentration, the net chemical flux of ozone (Pchem - Lchem) can be inferred from differences in ozone concentrations between adjacent monitoring sites. We show that ozone production rates, in general, increase with temperature. We also show that decreases in NOx emissions over the period from 2001-2007 have been effective at reducing ozone production at all points along the transect, but only on days where temperatures are highest. At low temperatures, this decrease is less apparent

  6. 77 FR 3664 - Drawbridge Operation Regulation; Sacramento River, CA

    Science.gov (United States)

    2012-01-25

    ... performed on this proposal to various waterway user organizations including the Pacific Inter-Club Yacht Association, the Recreational Boaters of California, the Capital City Yacht Club, the Sacramento Yacht Club, River View Yacht Club and Hornblower Cruises. The Coast Guard policy regarding the promulgation of...

  7. Comparison of implementation of selected TMI action plan requirements on operating plants designed by Babcock and Wilcox

    International Nuclear Information System (INIS)

    Thoma, J.O.

    1984-05-01

    This report provides the results of a study conducted by the US Nuclear Regulatory Commission staff to compare the degree to which eight Babcock and Wilcox (B and W) designed licensed nuclear power plants have complied with the requirements in NUREG-0737, Clarification of TMI Action Plan Requirements. The eight licensed operating plants examined are as follows: Arkansas Nuclear One Unit 1 (ANO-1), Crystal River Unit 3, Davis Besse, Oconee Units 1, 2, and 3, Rancho Seco, and Three Mile Island Unit 1 (TMI-1). The purpose of this audit was to establish the progress of the TMI-1 licensee, General Public Utilities (GPU) Nuclear Corporation, in completing the long-term requirements in NUREG-0737 relative to the other B and W licensees examined

  8. SELECCIÓN DE “CABEZAS DE CLON” EN CAFÉ ROBUSTA (Coffea canephora EN EL TRÓPICO SECO, ECUADOR

    Directory of Open Access Journals (Sweden)

    Luis Alberto Duicela Guambi

    2016-06-01

    Full Text Available La investigación se ejecutó de junio 2007 a diciembre 2012, en el Centro Experimental de café robusta ubicado en el Recinto Las Mercedes, cantón Isidro Ayora, provincia del Guayas, donde prevalece la zona de vida “Bosque muy seco tropical”. El objetivo fue seleccionar árboles “Cabezas de clon” de alto valor genético para impulsar la caficultura en el trópico seco del litoral ecuatoriano. Se evaluaron 32 accesiones de distinto origen, cada una conformada de 20 cafetos. En una primera etapa, se evaluaron los caracteres morfológicos y productivos de las accesiones y en una segunda etapa se incluyeron los atributos organolépticos e industriales de los árboles promisorios. El análisis estadístico incluyó el cálculo de estadígrafos, análisis de varianza, componentes principales y conglomerados jerárquicos. Los resultados permitieron identificar y seleccionar dos accesiones tipo conilón y siete tipo robusta. Las “cabezas de clon” seleccionadas fueron: CONERB-01-Planta 13-14-17-20, CON-ETP-01-Planta 11, COF-01-Plantas 02 y 04, COF-02-Plantas 15 y 17, COF-04-Planta 18, COF-05-Planta 2, COF-06-Plantas 3-15-17, NP-4024-Planta 15 y NP-2024-Planta 10. El potencial productivo de los árboles seleccionados varía de 2,5 a 3,9 t ha-1, por tanto, se infiere que existen genotipos de alta productividad, adaptados al trópico seco y al manejo intensivo con riego.

  9. Effects of Bank Revetment on Sacramento River, California

    Science.gov (United States)

    Michael D. Harvey; Chester C. Watson

    1989-01-01

    Twelve low radius of curvature bends, half of which were rivetted, were studied in the Butte Basin reach of Sacramento River, California, to determine whether bank revetment deleteriously affected salmonid habitat. At low discharge (128.6 cubic meters/s) it was demonstrated that revetment does not cause channel narrowing or deepening, nor does it prevent re-entrainment...

  10. Diel and seasonal movements by adult Sacramento pikeminnow (Ptychocheilus grandis) in the Eel River, northwestern California

    Science.gov (United States)

    Bret C. Harvey; Rodney J. Nakamoto

    1999-01-01

    Abstract - In late summer and fall, radio-tagged adult Sacramento pike-minnow (Ptychocheilus grandis) at three sites in the Eel River of northwestern California moved more at night than during the day. Fish moved up to 535 m at night and returned to their original positions the following morning. Adult Sacramento pikeminnow at all sites occupied only pools during the...

  11. Evaluación del rendimiento de grano seco en accesiones promisorias de Plukenetia volubilis “sacha inchi” en Loreto

    Directory of Open Access Journals (Sweden)

    Andrés Fernández-Sandoval

    2013-06-01

    Full Text Available El sacha inchi es una especie vegetal oleaginosa que se encuentra al estado silvestre en selva alta, baja y ceja de selva del Perú. Es importante por su alto contenido de ácidos grasos insaturados (aceites omegas y proteínas que contienen las semillas que lo hace ideal para mejorar la dieta alimenticia humana. El Gobierno Regional ha priorizado el cultivo de sacha inchi para impulsar el desarrollo económico y social de sus productores. Los trabajos de evaluación de rendimiento de grano seco de sacha inchi bajo condiciones de selva baja, se realizaron en el Campo Experimental El Dorado de la EEA. San Roque- INIA; con 9 accesiones provenientes del banco de germoplasma de la EEA. El Porvenir, Tarapoto. El objetivo de esta investigación fue evaluar el rendimiento de grano seco y validar y adaptar la tecnología de producción de esta especie en condiciones de selva baja. Las accesiones que sobresalieron fueron Barranquita y Cumbaza, con rendimientos de 1863 y 1809 kg/ha de grano seco por hectárea. La accesión Tambo Yaguas, obtuvo el rendimiento más bajo con 631 kg/ha de grano seco por hectárea, debido principalmente a su susceptibilidad a Rhizoctonia sp. “Mustia hilachoza”.

  12. Equal Educational Opportunity in the Sacramento City Unified School District; A Report to the Board of Education, The Sacramento City Unified School District.

    Science.gov (United States)

    Sacramento City Unified School District, CA. Citizens Advisory Committee on Equal Educational Opportunity.

    A 1965 report presents the findings of a citizens committee on racial tension and school segregation in Sacramento, California. Discussed are defacto segregation and its causes and effects, equal educational opportunity, the neighborhood school concept, and intergroup relations. A series of recommendations for improvement are included. (NH)

  13. Rhodomollacetals A-C, PTP1B Inhibitory Diterpenoids with a 2,3:5,6-Di-seco-grayanane Skeleton from the Leaves of Rhododendron molle.

    Science.gov (United States)

    Zhou, Junfei; Sun, Na; Zhang, Hanqi; Zheng, Guijuan; Liu, Junjun; Yao, Guangmin

    2017-10-06

    Three novel diterpenoids with an unprecedented 2,3:5,6-di-seco-grayanane carbon skeleton, rhodomollacetals A-C (1-3), are isolated from the leaves of Rhododendron molle. Their structures are elucidated by comprehensive spectroscopic techniques and single-crystal X-ray diffraction. Rhodomollacetal A (1) possesses a novel cis/cis/cis/cis-fused 6/6/6/6/5 pentacyclic ring system, featuring an unprecedented 11,13,18-trioxa-pentacyclo [8.7.1.1 5,8 .0 2,8 .0 12,17 ]nonadecane scaffold. Compounds 2 and 3 have a rare 4-oxatricyclo[7.2.1.0 1,6 ]dodecane moiety and a 2,3-dihydro-4H-pyran-4-one unit. Compounds 1-3 showed moderate PTP1B inhibitory activities, and their molecular dockings were investigated.

  14. Reactor control system upgrade for the McClellan Nuclear Radiation Center Sacramento, CA

    International Nuclear Information System (INIS)

    Power, M. A.

    1999-01-01

    Argonne National Laboratory is currently developing a new reactor control system for the McClellan Nuclear Radiation Facility. This new control system not only provides the same functionality as the existing control system in terms of graphic displays of reactor process variables, data archival capability, and manual, automatic, pulse and square-wave modes of operation, but adds to the functionality of the previous control system by incorporating signal processing algorithms for the validation of sensors and automatic calibration and verification of control rod worth curves. With the inclusion of these automated features, the intent of this control system is not to replace the operator but to make the process of controlling the reactor easier and safer for the operator. For instance, an automatic control rod calibration method reduces the amount of time to calibrate control rods from days to minutes, increasing overall reactor utilization. The control rod calibration curve, determined using the automatic calibration system, can be validated anytime after the calibration, as long as the reactor power is between 50W and 500W. This is done by banking all of the rods simultaneously and comparing the tabulated rod worth curves with a reactivity computer estimate. As long as the deviation between the tabulated values and the reactivity estimate is within a prescribed error band, then the system is in calibration. In order to minimize the amount of information displayed, only the essential flux-related data are displayed in graphical format on the control screen. Information from the sensor validation methods is communicated to the operators via messages, which appear in a message window. The messages inform the operators that the actual process variables do not correlate within the allowed uncertainty in the reactor system. These warnings, however, cannot cause the reactor to shutdown automatically. The reactor operator has the ultimate responsibility of using this

  15. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Massaro, Lawrence M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power reactor sites was conducted. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: (1) characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory, (2) a description of the on-site infrastructure and conditions relevant to transportation of SNF and GTCC waste, (3) an evaluation of the near-site transportation infrastructure and experience relevant to shipping transportation casks containing SNF and GTCC waste, including identification of gaps in information, and (4) an evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. Every site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an important source of information used to identify the transportation mode options for the sites. Especially important in conducting the evaluation were site visits, through which information was obtained that would not have been available otherwise. Extensive photographs taken during the site visits proved to be particularly useful in documenting the current conditions at or near the sites. It is expected that additional site visits will be conducted to add to the information presented in the evaluation.

  16. Interacciones entre semillas y escarabajos del estiércol (scarabaeinae en un bosque tropical seco

    Directory of Open Access Journals (Sweden)

    Julissa Ocampo-Castillo

    2018-01-01

    Full Text Available Los escarabajos del estiércol (Scarabaeinae son insectos importantes en muchos ecosistemas terrestres por susfunciones ecológicas, derivadas del comportamiento de remover las heces de vertebrados. Este grupo de insectoses particularmente abundante en los bosques tropicales (BT. Sus funciones ecológicas han sido principalmenteestudiadas en los BT húmedos, existiendo poca información para los BT secos. Se realizaron experimentos de campoen la Estación de Biología de Chamela (Jalisco, México durante la temporada de lluvias para cuantificar la remociónde heces por los escarabajos del estiércol y para evaluar sus interacciones con semillas durante la remoción deheces en un BT seco. A las 48 h la remoción de heces fue total; 71% de las semillas artificiales fueron enterradas entre0.5 y 30 cm de profundidad, y el 29% quedaron sobre la superficie pero dispersadas horizontalmente entre 1 y 150cm. El establecimiento de plántulas a partir del banco de semillas se vio favorecido por la presencia de heces y laactividad de los escarabajos del estiércol. Comparando nuestros resultados con aquellos obtenidos en bosquesNeotropicales húmedos, concluimos que en el BT seco estudiado las funciones ecológicas de los Scarabaeinae enla época de lluvias son similares a lo registrado en BT húmedos.

  17. Déficit de polinização da aceroleira no período seco no semiárido paraibano

    Directory of Open Access Journals (Sweden)

    Rozileudo da Silva Guedes

    2011-06-01

    Full Text Available A aceroleira é uma importante frutífera tropical que pode produzir frutos o ano todo na região semiárida do Nordeste do Brasil, caso seja utilizada a irrigação. Como a aceroleira depende da polinização por abelhas coletoras de óleos florais para apresentar uma produção satisfatória de frutos, este trabalho teve como objetivo avaliar a abundância de polinizadores e o sucesso reprodutivo da cultura no período seco, no semiárido paraibano. Foram registradas quatro espécies de abelhas nativas da tribo Centridini, todas consideradas polinizadoras efetivas da aceroleira, pela frequência nas flores e comportamento: Centris aenea Lepeletier, C. tarsata Smith, C. fuscata Lepeletier e C. trigonoides Lepeletier (Apidae, Centridini. A frequência de visitas às flores foi menor no período seco do que no período chuvoso. A polinização cruzada manual complementar resultou em incremento de 61 a 74% na produção de frutos durante o período seco, nos dois anos avaliados, indicando que há um grande déficit de polinização devido à baixa abundância de abelhas Centris. Esse resultado implica a necessidade de manejo dos polinizadores, especialmente em cultivos irrigados durante o período seco, na região semiárida do Nordeste do Brasil.

  18. Occurrence and transport of diazinon in the Sacramento River, California, and selected tributaries during three winter storms, January-February 2000

    Science.gov (United States)

    Dileanis, Peter D.; Bennett, Kevin P.; Domagalski, Joseph L.

    2002-01-01

    The organophosphate pesticide diazinon is applied as a dormant orchard spray in the Sacramento Valley, California, during the winter when the area receives a majority of its annual rainfall. Dormant spray pesticides, thus, have the potential to wash off the areas of application and migrate with storm runoff to streams in the Sacramento River Basin. Previous monitoring studies have shown that rain and associated runoff from winter storms plays an important role in the transport of diazinon from point of application to the Sacramento River and tributaries. Between January 30 and February 25, 2000, diazinon concentrations in the Sacramento River and selected tributaries were monitored on 5 consecutive days during each of three winter storms that moved through the Sacramento Valley after diazinon had been applied to orchards in the basin. Water samples were collected at 17 sites chosen to represent the effect of upstream land use at local and regional scales. Most samples were analyzed using an enzyme-linked immunosorbent assay (ELISA). Analysis by gas chromatography with electron capture detector and thermionic specific detector (GC/ECD/TSD) and gas chromatography with mass spectrometry (GC/MS) was done on split replicates from over 30 percent of the samples to confirm ELISA results and to provide lower analytical reporting limits at selected sites [30 ng/L (nanogram per liter) for ELISA, 20 ng/L for GC/ECD/TSD, and 2 ng/L for GC/MS]. Concentrations determined from ELISA analyses were consistently higher than concentrations for split samples analyzed by gas chromatography methods. Because of bias between diazinon concentrations using ELISA and gas chromatography methods, results from ELISA analyses were not compared to water-quality criteria. Load calculations using the ELISA analyses are similarly biased. Because the bias was consistent, however, the ELISA data is useful in site-to-site comparisons used to rank the relative levels and contributions of diazinon from

  19. Brief account of the effect of overcooling accidents on the integrity of PWR pressure vessels

    International Nuclear Information System (INIS)

    Cheverton, R.D.

    1982-01-01

    The occurrence in recent years of several (PWR) accident initiating events that could lead to severe thermal shock to the reactor pressure vessel, and the growing awareness that copper and nickel in the vessel material significantly enhance radiation damage in the vessel, have resulted in a reevaluation of pressure-vessel integrity during postulated overcooling accidents. Analyses indicate that the accidents of concern are those involving both thermal shock and pressure loadings, and that an accident similar to that at Rancho Seco in 1978 could, under some circumstances and at a time late in the normal life of the vessel, result in propagation of preexistent flaws in the vessel wall to the extent that they might completely penetrate the wall. More severe accidents have been postulated that would result in even shorter permissible lifetimes. However, the state-of-the-art fracture-mechanics analysis may contain excessive conservatism, and this possibility is being investigated. Furthermore, there are several remedial measures, such as fuel shuffling, to reduce the damage rate, and vessel annealing, to restore favorable material properties, that may be practical and used if necessary. 5 figures

  20. Groundwater quality in the Southern Sacramento Valley, California

    Science.gov (United States)

    Bennett, George L.; Fram, Miranda S.; Belitz, Kenneth

    2011-01-01

    Groundwater provides more than 40 percent of California's drinking water. To protect this vital resource, the State of California created the Groundwater Ambient Monitoring and Assessment (GAMA) Program. The Priority Basin Project of the GAMA Program provides a comprehensive assessment of the State's groundwater quality and increases public access to groundwater-quality information. The Southern Sacramento Valley is one of the study units being evaluated.

  1. Groundwater quality in the Northern Sacramento Valley, California

    Science.gov (United States)

    Bennett, George L.; Fram, Miranda S.; Belitz, Kenneth

    2011-01-01

    Groundwater provides more than 40 percent of California's drinking water. To protect this vital resource, the State of California created the Groundwater Ambient Monitoring and Assessment (GAMA) Program. The Priority Basin Project of the GAMA Program provides a comprehensive assessment of the State's groundwater quality and increases public access to groundwater-quality information. The Northern Sacramento Valley is one of the study units being evaluated.

  2. Proposed strategy for improving capulín cultivation in the municipalities of Domingo Arenas, Calpan and San Nicolas de los Ranchos

    OpenAIRE

    Luz María Páez Reyes; Josset Sánchez Olarte; Mariano Velasco Torres; Adrián Argumedo Macías; Jesús Felipe Álvarez Gaxiola

    2013-01-01

    Currently the municipalities of Domingo Arenas, Calpan and San Nicolás de los Ranchos Puebla State, conditions and have a favorable climate for growing capulín, however, not being given adequate management value the crop, This causes the yields are low and its economic importance is unnoticed. The aim of the investigation was "explore how to improve the economic and productive use capulín through the revaluation of the same by the producers, because of the advantages offered by the cultivati...

  3. Síndrome de ojo seco Dry eye syndrome

    Directory of Open Access Journals (Sweden)

    Rafael Balbona Brito

    2005-06-01

    Full Text Available Se realizó una revisión bibliográfica sobre el síndrome de ojo seco, que abarcó su clasificación, diagnóstico y tratamiento. Se tuvo en cuenta que constituye una entidad frecuente en la Oftalmología; se presenta con la finalidad de mostrar el síndrome de manera actualizada y con el objetivo de facilitar su manejoA bibliographic review of the dry eye syndrome that included its classification, diagnosis and treatment is made. Taking into account that it is a frequent entity in Ophthalmology, it is presented in order to provide an updating of the syndrome and to facilitate its management

  4. The contribution of rice agriculture to methylmercury in surface waters: A review of data from the Sacramento Valley, California

    Science.gov (United States)

    Tanner, K. Christy; Windham-Myers, Lisamarie; Fleck, Jacob; Tate, Kenneth W.; McCord, Stephen A.; Linquist, Bruce A.

    2017-01-01

    Methylmercury (MeHg) is a bioaccumulative pollutant produced in and exported from flooded soils, including those used for rice (Oriza sativa L.) production. Using unfiltered aqueous MeHg data from MeHg monitoring programs in the Sacramento River watershed from 1996 to 2007, we assessed the MeHg contribution from rice systems to the Sacramento River. Using a mixed-effects regression analysis, we compared MeHg concentrations in agricultural drainage water from rice-dominated regions (AgDrain) to MeHg concentrations in the Sacramento and Feather Rivers, both upstream and downstream of AgDrain inputs. We also calculated MeHg loads from AgDrains and the Sacramento and Feather Rivers. Seasonally, MeHg concentrations were higher during November through May than during June through October, but the differences varied by location. Relative to upstream, November through May AgDrain least-squares mean MeHg concentration (0.18 ng L−1, range 0.15–0.23 ng L−1) was 2.3-fold higher, while June through October AgDrain mean concentration (0.097 ng L−1, range 0.6–1.6 ng L−1) was not significantly different from upstream. June through October AgDrain MeHg loads contributed 10.7 to 14.8% of the total Sacramento River MeHg load. Missing flow data prevented calculation of the percent contribution of AgDrains in November through May. At sites where calculation was possible, November through May loads made up 70 to 90% of the total annual load. Elevated flow and MeHg concentration in November through May both contribute to the majority of the AgDrain MeHg load occurring during this period. Methylmercury reduction efforts should target elevated November through May MeHg concentrations in AgDrains. However, our findings suggest that the contribution and environmental impact of rice is an order of magnitude lower than previous studies in the California Yolo Bypass.

  5. Distribución espacial del Bosque Seco Tropical en el Valle del Cauca, Colombia

    Directory of Open Access Journals (Sweden)

    Diana Patricia Alvarado-Solano

    2015-09-01

    Full Text Available En el departamento del Valle del Cauca, la distribución de Bosque Seco Tropical (BsT se ha asociado al valle geográfico del río Cauca ubicado en la zona plana. Actualmente en esta zona, su cobertura se ha reducido a pocos relictos que se encuentran bajo alguna figura de conservación y mantienen áreas representativas de las formaciones vegetales sssstípicas de este bioma. Este trabajo se enfocó en el reconocimiento de la distribución espacial de formaciones vegetales de BsT en el departamento del Valle del Cauca. Se empleó información cartográfica secundaria para reconocer los biomas, ecosistemas y usos del suelo del área de estudio y en zonas adyacentes del piedemonte y montañas. Un modelo digital de elevaciones fue utilizado para realizar análisis altitudinales. En un sistema de información geográfico se aplicaron técnicas de geoprocesamiento y análisis geoespacial entre la información cartográfica y satelital. Los resultados evidencian que pese al avanzado deterioro de las coberturas de bosque seco en la zona plana, alrededor del 80 % se localiza en ecosistemas de montaña, específicamente en zonas de transición hacia bosques húmedos. A futuro, el potencial de estas áreas deberá evaluarse para ser incluidas en estrategias de conservación y restauración del bosque seco así como en el diseño de procesos adaptativos frente al cambio climático.

  6. Groundwater budgets for Detrital, Hualapai, and Sacramento Valleys, Mohave County, Arizona, 2007-08

    Science.gov (United States)

    Garner, Bradley D.; Truini, Margot

    2011-01-01

    The United States Geological Survey, in cooperation with the Arizona Department of Water Resources, initiated an investigation of the hydrogeology and water resources of Detrital, Hualapai, and Sacramento Valleys in northwestern Arizona in 2005, and this report is part of that investigation. Water budgets were developed for Detrital, Hualapai, and Sacramento Valleys to provide a generalized understanding of the groundwater systems in this rural area that has shown some evidence of human-induced water-level declines. The valleys are within the Basin and Range physiographic province and consist of thick sequences of permeable alluvial sediment deposited into basins bounded by relatively less permeable igneous and metamorphic rocks. Long-term natural recharge rates (1940-2008) for the alluvial aquifers were estimated to be 1,400 acre-feet per year (acre-ft/yr) for Detrital Valley, 5,700 acre-ft/yr for Hualapai Valley, and 6,000 acre-ft/yr for Sacramento Valley. Natural discharge rates were assumed to be equal to natural recharge rates, on the basis of the assumption that all groundwater withdrawals to date have obtained water from groundwater storage. Groundwater withdrawals (2007-08) for the alluvial aquifers were less than 300 acre-ft/yr for Detrital Valley, about 9,800 acre-ft/yr for Hualapai Valley, and about 4,500 acre-ft/yr for Sacramento Valley. Incidental recharge from leaking water-supply pipes, septic systems, and wastewater-treatment plants accounted for about 35 percent of total recharge (2007-08) across the study area. Natural recharge and discharge values in this study were 24-50 percent higher than values in most previously published studies. Water budgets present a spatially and temporally "lumped" view of water resources and incorporate many sources of uncertainty in this study area where only limited data presently are available.

  7. Sensitivity of SWOT discharge algorithm to measurement errors: Testing on the Sacramento River

    Science.gov (United States)

    Durand, Micheal; Andreadis, Konstantinos; Yoon, Yeosang; Rodriguez, Ernesto

    2013-04-01

    Scheduled for launch in 2019, the Surface Water and Ocean Topography (SWOT) satellite mission will utilize a Ka-band radar interferometer to measure river heights, widths, and slopes, globally, as well as characterize storage change in lakes and ocean surface dynamics with a spatial resolution ranging from 10 - 70 m, with temporal revisits on the order of a week. A discharge algorithm has been formulated to solve the inverse problem of characterizing river bathymetry and the roughness coefficient from SWOT observations. The algorithm uses a Bayesian Markov Chain estimation approach, treats rivers as sets of interconnected reaches (typically 5 km - 10 km in length), and produces best estimates of river bathymetry, roughness coefficient, and discharge, given SWOT observables. AirSWOT (the airborne version of SWOT) consists of a radar interferometer similar to SWOT, but mounted aboard an aircraft. AirSWOT spatial resolution will range from 1 - 35 m. In early 2013, AirSWOT will perform several flights over the Sacramento River, capturing river height, width, and slope at several different flow conditions. The Sacramento River presents an excellent target given that the river includes some stretches heavily affected by management (diversions, bypasses, etc.). AirSWOT measurements will be used to validate SWOT observation performance, but are also a unique opportunity for testing and demonstrating the capabilities and limitations of the discharge algorithm. This study uses HEC-RAS simulations of the Sacramento River to first, characterize expected discharge algorithm accuracy on the Sacramento River, and second to explore the required AirSWOT measurements needed to perform a successful inverse with the discharge algorithm. We focus on the sensitivity of the algorithm accuracy to the uncertainty in AirSWOT measurements of height, width, and slope.

  8. Reservoir Operating Rule Optimization for California's Sacramento Valley

    Directory of Open Access Journals (Sweden)

    Timothy Nelson

    2016-03-01

    Full Text Available doi: http://dx.doi.org/10.15447/sfews.2016v14iss1art6Reservoir operating rules for water resource systems are typically developed by combining intuition, professional discussion, and simulation modeling. This paper describes a joint optimization–simulation approach to develop preliminary economically-based operating rules for major reservoirs in California’s Sacramento Valley, based on optimized results from CALVIN, a hydro-economic optimization model. We infer strategic operating rules from the optimization model results, including storage allocation rules to balance storage among multiple reservoirs, and reservoir release rules to determine monthly release for individual reservoirs. Results show the potential utility of considering previous year type on water availability and various system and sub-system storage conditions, in addition to normal consideration of local reservoir storage, season, and current inflows. We create a simple simulation to further refine and test the derived operating rules. Optimization model results show particular insights for balancing the allocation of water storage among Shasta, Trinity, and Oroville reservoirs over drawdown and refill seasons, as well as some insights for release rules at major reservoirs in the Sacramento Valley. We also discuss the applicability and limitations of developing reservoir operation rules from optimization model results.

  9. THE BACKYARD OF THE CORN FARMERS. SAN NICOLÁS DE LOS RANCHOS, PUEBLA-MÉXICO

    Directory of Open Access Journals (Sweden)

    José Luis López González

    2013-04-01

    Full Text Available This research aimed to identify the contribution that the backyards of corn farmers make to food security and the preservation and conservation of plant and animal diversity, and its link with farmers' knowledge, in San Nicolas de los Ranchos. To this end, 77 producers surveyed randomly selected corn was calculated using an equation, the role of food security in the backyard, and the calculation of the diversity index and species richness that helped expose the plant diversity found also estimated the amount of dung that provide animals to backyard farming, this helped to show synergy livestock farming. Some results suggest that the products obtained in the backyard contribute to feeding the family. Also found plant and animal diversity, as are most ornamental plants, food and medicinal use, it is also possible to identify animals such as chickens, turkeys, sheep, goats, cows, horses and donkeys.

  10. Radioactive hydrogeochemical processes in the Chihuahua-Sacramento Basin, Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Burillo, J. C.; Reyes C, M.; Montero C, M. E.; Renteria V, M.; Herrera P, E. F. [Centro de Investigacion en Materiales Avanzados, S. C., Miguel de Cervantes No. 120, Complejo Industrial Chihuahua, 31109 Chihuahua (Mexico); Reyes, I.; Espino, M. S., E-mail: elena.montero@cimav.edu.mx [Universidad Autonoma de Chihuahua, Facultad de Ingenieria, Nuevo Campus Universitario, Chihuahua (Mexico)

    2012-06-15

    The Chihuahua Basin is divided by its morphology into three main sub basins: Chihuahua-Sacramento sub basin, Chihuahua Dam sub basin and Chuviscar River sub basin. In the aquifers at the Sacramento sub basin, specific concentrations of uranium in groundwater range from 460 to 1260 Bq / m{sup 3}. The presence of strata and sandy clay lenses with radiometric anomalies in the N W of Chihuahua Valley was confirmed by a litostatigraphic study and gamma spectrometry measurements of drill cuttings. High uranium activity values found in the water of some deep wells may correspond to the presence of fine material bodies of carbonaceous material, possible forming pa leo-sediment of flooding or pa leo-soils. It is suggested that these clay horizons are uranyl ion collectors. Uranyl may suffer a reduction process by organic material. Furthermore the groundwater, depending on its ph and Eh, oxidizes and re-dissolves uranium. The hydrogeochemical behavior of San Marcos dam and the N W Valley area is the subject of studies that should help to clarify the origin of the radioactive elements and their relationships with other pollutants in the watershed. (Author)

  11. Radioactive hydrogeochemical processes in the Chihuahua-Sacramento Basin, Mexico

    International Nuclear Information System (INIS)

    Burillo, J. C.; Reyes C, M.; Montero C, M. E.; Renteria V, M.; Herrera P, E. F.; Reyes, I.; Espino, M. S.

    2012-01-01

    The Chihuahua Basin is divided by its morphology into three main sub basins: Chihuahua-Sacramento sub basin, Chihuahua Dam sub basin and Chuviscar River sub basin. In the aquifers at the Sacramento sub basin, specific concentrations of uranium in groundwater range from 460 to 1260 Bq / m 3 . The presence of strata and sandy clay lenses with radiometric anomalies in the N W of Chihuahua Valley was confirmed by a litostatigraphic study and gamma spectrometry measurements of drill cuttings. High uranium activity values found in the water of some deep wells may correspond to the presence of fine material bodies of carbonaceous material, possible forming pa leo-sediment of flooding or pa leo-soils. It is suggested that these clay horizons are uranyl ion collectors. Uranyl may suffer a reduction process by organic material. Furthermore the groundwater, depending on its ph and Eh, oxidizes and re-dissolves uranium. The hydrogeochemical behavior of San Marcos dam and the N W Valley area is the subject of studies that should help to clarify the origin of the radioactive elements and their relationships with other pollutants in the watershed. (Author)

  12. 78 FR 66058 - Habitat Conservation Plan for South Sacramento County, California

    Science.gov (United States)

    2013-11-04

    ... scoping meetings in local news media and on the Internet at http://www.fws.gov/sacramento . ADDRESSES... sphere of influence; and land within Galt's adopted sphere of influence. Almost all ground disturbance... resources, transportation, air quality, land use, recreation, water use, local economy, and environmental...

  13. Influência do processo de secagem e condição de armazenamento de extratos secos de Bauhinia forficata e Passiflora alata sobre seu perfil de dissolução

    Directory of Open Access Journals (Sweden)

    C.R.F. SOUZA

    2015-03-01

    Full Text Available No Brasil, os produtos fitoterápicos são considerados medicamentos, sendo necessário o estabelecimento de estudos que assegurem a manutenção dos requisitos de qualidade durante o processamento e o armazenamento. Testes de dissolução podem ser empregados para se estimar a biodisponibilidade de um fármaco, sendo uma análise rotineira no desenvolvimento e controle de qualidade de medicamentos alopáticos. A determinação do perfil de dissolução de fitoterápicos também pode ser um importante critério para avaliação da sua qualidade lote-a-lote, bem como para os estudos de desenvolvimento e de estabilidade. O objetivo deste trabalho foi investigar a influência dos métodos de secagem e da condição de armazenagem sobre os perfis de dissolução dos flavonoides totais de extratos secos de duas plantas medicinais bastante difundidas no Brasil, a Bauhinia forficata e a Passiflora alata. Os extratos secos foram produzidos pelo processo de secagem em leito de jorro e em spray drying, sendo submetidos a condições de armazenagem aceleradas (temperatura de 40 ± 2ºC e umidade relativa de 75 ± 5%, por um período de 90 dias. Os perfis de dissolução foram obtidos para amostras de extratos secos antes e após o período de armazenamento. O teor de flavonoides totais foi quantificado por espectrofotometria. Os extratos secos de B. forficata e P. alata apresentaram adequada liberação de flavonoides nos ensaios de dissolução. Os extratos secos de Passiflora alata apresentaram completa dissolução dos flavonoides, 92% e 98% dos teores originais após 60 minutos de ensaio, respectivamente para o extrato seco em leito de jorro e em spray drying.

  14. PARR-2: reactor description and experiments

    International Nuclear Information System (INIS)

    Wyne, M.F.; Meghji, J.H.

    1990-12-01

    PARR-2 is a miniature neutron source reactor (MNSR) research reactor has been designed at the rate of 27 kW. Reactor assembly comprises of peaking characteristics with a self limiting flux. In this report reactor description with its assembly and instrumentation control system has been explained. The reactor engineering and physics experiments which can be performed on this reactor are explained in this report. PARR-2 is fueled with HEU fuel pins which are about 90% enriched in U-235. Specific requirements for the safety of the reactor, its building and the personnel, normal instrumentation as required in an industrial environment is sufficient. (A.B.)

  15. Reactor BR2: Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

    The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. A safety audit was conduced by the IAEA, the conclusions of which demonstrated the excellent performance of the plant in terms of operational safety. In 1999, the CALLISTO facility was extensively used for various programmes involving LWR pressure vessel materials, IASCC of LWR structural materials, fusion reactor materials and martensic steels for use in ADS systems. In 1999, BR2's commercial programmes were further developed

  16. Material test reactor fuel research at the BR2 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Dyck, Steven Van; Koonen, Edgar; Berghe, Sven van den [Institute for Nuclear Materials Science, SCK-CEN, Boeretang, Mol (Belgium)

    2012-03-15

    The construction of new, high performance material test reactor or the conversion of such reactors' core from high enriched uranium (HEU) to low enriched uranium (LEU) based fuel requires several fuel qualification steps. For the conversion of high performance reactors, high density dispersion or monolithic fuel types are being developed. The Uranium-Molybdenum fuel system has been selected as reference system for the qualification of LEU fuels. For reactors with lower performance characteristics, or as medium enriched fuel for high performance reactors, uranium silicide dispersion fuel is applied. However, on the longer term, the U-Mo based fuel types may offer a more efficient fuel alternative and-or an easier back-end solution with respect to the silicide based fuels. At the BR2 reactor of the Belgian nuclear research center, SCK-CEN in Mol, several types of fuel testing opportunities are present to contribute to such qualification process. A generic validation test for a selected fuel system is the irradiation of flat plates with representative dimensions for a fuel element. By flexible positioning and core loading, bounding irradiation conditions for fuel elements can be performed in a standard device in the BR2. For fuel element designs with curved plates, the element fabrication method compatibility of the fuel type can be addressed by incorporating a set of prototype fuel plates in a mixed driver fuel element of the BR2 reactor. These generic types of tests are performed directly in the primary coolant flow conditions of the BR2 reactor. The experiment control and interpretation is supported by detailed neutronic and thermal-hydraulic modeling of the experiments. Finally, the BR2 reactor offers the flexibility for irradiation of full size prototype fuel elements, as 200mm diameter irradiation channels are available. These channels allow the accommodation of various types of prototype fuel elements, eventually using a dedicated cooling loop to provide the

  17. EBR-2 [Experimental Breeder Reactor-2], IFR [Integral Fast Reactor] prototype testing programs

    International Nuclear Information System (INIS)

    Lehto, W.K.; Sackett, J.I.; Lindsay, R.W.; Planchon, H.P.; Lambert, J.D.B.

    1990-01-01

    The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development. (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs

  18. Combined Modular Pumped Hydro Energy Storage Plus Solar PV Proposal for Rio Rancho High School, New Mexico

    Energy Technology Data Exchange (ETDEWEB)

    Bibeault, Mark Leonide [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-08-25

    This is a proposal to locate a combined Modular Pumped Hydro (MPH) Energy Storage plus PV solar facility at Rio Rancho High School, NM. The facility will functionally provide electricity at night derived from renewable solar energy. Additionally the facility will provide STEM related educational opportunities for students and staff of the school, public community outreach, and validation of an energy storage approach applicable for the Nation (up to 1,000,000 kWh per installation). The proposal will summarize the nature of electricity, why energy storage is useful, present the combined MPH and solar PV production design, present how the actual design will be built and operated in a sustainable manner, how the project could be funded, and how the project could be used in STEM related activities.

  19. IDENTIFICACIÓN, USOS Y MEDICIÓN DE LEGUMINOSAS ARBÓREAS FORRAJERAS EN RANCHOS GANADEROS DEL SUR DEL ESTADO DE MÉXICO

    Directory of Open Access Journals (Sweden)

    Jaime Olivares Pérez

    2011-06-01

    Full Text Available El objetivo del trabajo fue identificar las especies arbóreas leguminosas, usos, densidad, frecuencia, abundancia y medidas dasométricas en ranchos ganaderos del sur del Estado de México; así como evaluar la producción de follaje (kg materia seca árbol-1ha-1 de Pithecellobium dulce, Haematoxylum brasiletto y Gliricidia sepium —preferidas por los ganaderos como fuente de forraje y con mayor densidad—; y evaluar  la producción de fruto (kg materia seca  árbol-1ha-1 de Acacia  cochliacantha y P. dulce. La información de usos se obtuvo mediante entrevistas semiestructuradas aplicadas a 69 ganaderos, cantidad que representó 83% de la población. Las mediciones de los árboles se realizaron en seis ranchos mediante trabajo de campo. La información se analizó usando estadísticas descriptivas. Se identificaron 12 especies arbóreas (Acacia cochliacantha, Lysiloma divaricata, Pithecellobium dulce, Haematoxylum brasiletto y Gliricidia sepium, las cuales presentaron mayor densidad, frecuencia y abundancia. De 46.6% de las arbóreas, su follaje y fruto es consumido por rumiantes; de 20%, es consumido follaje, fruto y flor. Se proporcionan de cinco a ocho usos en 80% de las especies, además del forrajero, como leña, poste, sombra, cerca viva, medicinal, consumo humano, artesanal y maderable. Las arbóreas con mayor fuste fueron: Caesalpinia coriaria, Pithecellobium dulce, Enterolobium cyclocarpum y Leucaena esculenta, con diámetro basal (DB de 47.11 a 57.2 cm, diámetro a la altura del pecho (DAP de 49.34 a 50.3 cm y altura (A de 7.4 a 14.5 m,  los cuales son preferidos para sombra. La producción de follaje de Pithecellobium dulce, Haematoxylum brasiletto y Gliricidia sepium fue de 44.5, 8.8 y 8.4 kg MS arbol-1, respectivamente. La producción de fruto de Pithecellobium dulce y Acacia cochliacantha fue 63.9 y 21.7 kg MS árbol-1, respectivamente. Las 12 leguminosas

  20. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2001-01-01

    The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given

  1. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2001-04-01

    The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given.

  2. Evaluation for reasonableness of power conversion system concepts in the gas turbine high temperature reactor (GTHTR300)

    International Nuclear Information System (INIS)

    Minatsuki, I.; Mizokami, Y.

    2007-01-01

    The conceptual design study for the Gas Turbine High Temperature Reactor (GTHTR300) was completed in 2004. In GTHTR300, SECO (Simple, Economical Competitiveness and Originality) is advocated as design philosophy in order to minimize technical and economical requirement. Furthermore the design of the GTHTR300 was developed with reflecting various view points from utilities, manufacturers and research organizations. In GTHTR300, the horizontal turbo machine rotor, the turbo machine in a separated vessel, the turbo machine with single rotor, the generator inside the power conversion vessel, and the power conversion system without inter-coolers were selected as major power conversion system concepts. This paper describes the investigation and analysis about the major concepts of GTHTR300 power conversion system in order to evaluate reasonableness of GTHTR300 design approach and acceptability with using experience and engineering knowledge of Mitsubishi Heavy Industries, Ltd., which were accumulated through the activities of HTGR-GT and HTTR (High Temperature Engineering Test Reactor) designing, manufacturing, fabricating and testing. From the result of the evaluation, it was concluded that the selection of each concept in GTHTR300 was reasonable as based on the original design philosophy SECO. As a conclusion, we expect the GTHTR300 to become one of the most promising concepts for commercialization in near future. (authors)

  3. Biogeochemical studies of wintering waterfowl in the Imperial and Sacramento Valleys

    Energy Technology Data Exchange (ETDEWEB)

    Koranda, J.J.; Stuart, M.; Thompson, S.; Conrado, C.

    1979-10-01

    Trace and major elemental composition were determined in the organs of wintering waterfowl in the Imperial and Sacramento Valleys of California, and in soils, sediments, and agricultural fertilizer that constitute the various sources of elements in the waterfowl. These data provide a biogeochemical baseline for waterfowl populations wintering in an area being developed for geothermal power. This baseline in the Imperial Valley is affected by soil and sediment composition, agricultural effluents in irrigation and stream water, and spent shot deposited by hunters in waterfowl habitats. The waterfowl acquire a set of trace elements from these sources and concentrations increase in their organs over the wintering period. Nickel, arsenic, selenium, bromine, and lead are the primary elements acquired from soil sources, agricultural effluents, and spent shot in the Imperial Valley. The assessment of effects from geothermal effluents on waterfowl populations in complex because there are large influxes of materials into the Imperial Valley ecosystem that contain trace elements, i.e., irrigation water, phosphatic fertilizers, pesticides, and lead shot. Multiple sources exist for many elements prominent in the expected geothermal effluents. The relationships between the two California valleys, the Imperial and Sacramento, are apparent in the trace element concentrations in the organs of waterfowl obtained in those two valleys. Arsenic is absent in the waterfowl organs obtained in the Sacramento Valley and relatively common in the Imperial Valley waterfowl. The effect of any release of geothermal effluent in the Imperial Valley waterfowl habitats will be difficult to describe because of the complexity of the biogeochemical baseline and the multiple sources of trace and major elements in the ecosystem.

  4. PWR pressure vessel integrity during overcooling accidents

    International Nuclear Information System (INIS)

    Cheverton, R.D.

    1981-01-01

    Pressurized water reactors are susceptible to certain types of hypothetical accidents that under some circumstances, including operation of the reactor beyond a critical time in its life, could result in failure of the pressure vessel as a result of propagation of crack-like defects in the vessel wall. The accidents of concern are those that result in thermal shock to the vessel while the vessel is subjected to internal pressure. Such accidents, referred to as pressurized thermal shock or overcooling accidents (OCA), include a steamline break, small-break LOCA, turbine trip followed by stuck-open bypass valves, the 1978 Rancho Seco and the TMI accidents and many other postulated and actual accidents. The source of cold water for the thermal shock is either emergency core coolant or the normal primary-system coolant. ORNL performed fracture-mechanics calculations for a steamline break in 1978 and for a turbine-trip case in 1980 and concluded on the basis of the results that many more such calculations would be required. To meet the expected demand in a realistic way a computer code, OCA-I, was developed that accepts primary-system temperature and pressure transients as input and then performs one-dimensional thermal and stress analyses for the wall and a corresponding fracture-mechanics analysis for a long axial flaw. The code is briefly described, and its use in both generic and specific plant analyses is discussed

  5. Safety features of TR-2 reactor

    International Nuclear Information System (INIS)

    Tuerker, T.

    2001-01-01

    TR-2 is a swimming pool type research reactor with 5 MW thermal power and uses standard MTR plate type fuel elements. Each standard fuel element consist of 23 fuel plates with a meat + cladding thickness of 0.127 cm, coolant channel clearance is 0.21 cm. Originally TR-2 is designed for %93 enriched U-Al. Alloy fuel meat.This work is based on the preparation of the Final Safety Analyses Report (FSAR) of the TR-2 reactor. The main aspect is to investigate the behaviour of TR-2 reactor under the accident and abnormal operating conditions, which cowers the accident spectrum unique for the TR-2 reactor. This presentation covers some selected transient analyses which are important for the safety aspects of the TR-2 reactor like reactivity induced startup accidents, pump coast down (Loss of Flow Accident, LOFA) and other accidents which are charecteristic to the TR-2

  6. Comportamento higroscópico do extrato seco de urucum (Bixa Orellana L Hygroscopic behavior of annatto (Bixa Orellana L dried extract

    Directory of Open Access Journals (Sweden)

    George Carlos dos Santos Anselmo

    2008-12-01

    Full Text Available Neste trabalho, objetivou-se determinar a higroscopicidade do urucum na forma de extrato seco. Neste estudo foram obtidas as atividades de água do extrato seco de urucum para as temperaturas de 10 a 50ºC e teores de água entre 6 e 22% base úmida. A metodologia empregada para as determinações foi o método dinâmico em que se utilizou o equipamento Thermoconstanter Novasina TH-2. Para os resultados experimentais aplicaram-se as equações propostas por Henderson modificada por Thompson e Henderson modificada por Cavalcanti Mata e Peleg. Por meio das análises dos parâmetros encontrados concluiu-se que a equação que melhor se ajusta aos dados experimentais é a equação de Henderson modificada por Cavalcanti Mata e que as isotermas de adsorção de água do extrato de urucum seco se comportaram sigmoidalmente, sendo consideradas do tipo II.The objective of this work was to verify the higroscopicity of annatto seeds in the dry extract form. The isotherms were determined by the dynamic method with the Thermoconstanter Novasina TH-2 equipment. The equilibrium temperatures were 10, 20, 30, 40 and 50 ºC to range of moisture content between 6 and 22%, wet basis. The equations proposed by Henderson modified by Thompson and Henderson modified by Cavalcanti Mata and Peleg were applied to the experimental data. Through the gotten parameters found concluded that the best equation to represent the experimental data is the Henderson equations modified by Cavalcanti Mata. It was also concluded that hygroscopic equilibrium isotherms of annatto seeds presented sigmoid forms, considered type II.

  7. Diversidad preliminar de Artrópodos en los remanentes de bosques secos andinos del Valle del Chota en el norte del Ecuador

    OpenAIRE

    Troya, Adrián; Bersosa, Fabián; Vega, Mauricio

    2012-01-01

    En este artículo se da a conocer sobre los bosques secos que representan el 42% de todos los bosques tropicales y se encuentran en peligro de destrucción. Las investigaciones en los bosques secos de Ecuador son puntuales en aspectos botánicos y ecológicos. Durante la época seca se muestreó dos localidades en el Valle del Chota con el objetivo de conocer la diversidad de artrópodos terrestres. Se colectaron 282 morfo-especies pertenecientes a 128 familias de artrópodos correspondientes a 22 ór...

  8. Diversidad de árboles y arbustos en fragmentos de bosque seco tropical en río Hato, Panamá

    Directory of Open Access Journals (Sweden)

    Omar R Lopez

    2015-01-01

    Full Text Available En fragmentos de bosque seco tropical en Río Hato, Panamá, estudiamos la composición florística según los árboles y arbustos. Establecimos 61 parcelas de 100 m2 distribuidas de forma aleatoria, totalizando 0.61 hectáreas. En cada unidad de muestreo medimos todos los individuos presentes con un DAP >5.0 cm. Encontramos un total de 52 especies de árboles representadas en veinticinco familias, de las cuales Fabaceae, Burseraceae, Myrtaceae y Rubiaceae aportan mayor número de especies (~35%. La especie Sloanea terniflora (Sessé & Moç. ex DC. Standl se encontró en más del 60.6% de los cuadrantes estudiados y resultó además ser la especie con mayor dominancia relativa (23%, seguida de Anacardium excelsum (Bertero & Balb. ex Kunth Skeels, que con solo quince individuos de grandes diámetros presentó una dominancia relativa del 10%. La diversidad promedio reveló índices intermedios (3.13 índice de Shannon. A pesar del bajo número de especies en comparación con otros BS-T de la región, los fragmentos en Río Hato conservan elementos florísticos de importancia ecológica y para la conservación de los bosques secos. Garcinia madruno (Kunth Hammel, una de las especies más abundante es clave en la producción de frutos para la fauna. Otras especies de importancia son Manilkara sapota (L. P. Royen y Copaifera aromatica Dwyer, las cuales aún son utilizadas como recurso maderero. Es prioritario para Panamá establecer estrategias de conservación que salvaguarden estos fragmentos como fuente de especies del bosque seco tropical y refugio para la vida silvestre.

  9. Reactor BR2. Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2002-01-01

    The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system

  10. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2002-04-01

    The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system.

  11. Sacramento River, Chico Landing to Red Bluff, California Bank Protection Project

    Science.gov (United States)

    1975-01-01

    i onwi de X X X X X X X (Turdus migratorius) Ruby-crowned kinglet Common-Nat i onwide X X X X X (Regulus calendula ) Water pipit Common-Nat i...City. In addition, State Point of Historical Interest, Glenn-011, Swifts Point, is located on the Sacramento River near Hamilton City and Glenn- Oil

  12. BR2 Reactor: Introduction

    International Nuclear Information System (INIS)

    Moons, F.

    2007-01-01

    The irradiations in the BR2 reactor are in collaboration with or at the request of third parties such as the European Commission, the IAEA, research centres and utilities, reactor vendors or fuel manufacturers. The reactor also contributes significantly to the production of radioisotopes for medical and industrial applications, to neutron silicon doping for the semiconductor industry and to scientific irradiations for universities. Along the ongoing programmes on fuel and materials development, several new irradiation devices are in use or in design. Amongst others a loop providing enhanced cooling for novel materials testing reactor fuel, a device for high temperature gas cooled fuel as well as a rig for the irradiation of metallurgical samples in a Pb-Bi environment. A full scale 3-D heterogeneous model of BR2 is available. The model describes the real hyperbolic arrangement of the reactor and includes the detailed 3-D space dependent distribution of the isotopic fuel depletion in the fuel elements. The model is validated on the reactivity measurements of several tens of BR2 operation cycles. The accurate calculations of the axial and radial distributions of the poisoning of the beryllium matrix by 3 He, 6 Li and 3T are verified on the measured reactivity losses used to predict the reactivity behavior for the coming decades. The model calculates the main functionals in reactor physics like: conventional thermal and equivalent fission neutron fluxes, number of displacements per atom, fission rate, thermal power characteristics as heat flux and linear power density, neutron/gamma heating, determination of the fission energy deposited in fuel plates/rods, neutron multiplication factor and fuel burn-up. For each reactor irradiation project, a detailed geometry model of the experimental device and of its neighborhood is developed. Neutron fluxes are predicted within approximately 10 percent in comparison with the dosimetry measurements. Fission rate, heat flux and

  13. Analysis of available wind resources and their suitability for hydrogen production in the Sacramento area

    International Nuclear Information System (INIS)

    Bartholomy, O.J.

    2004-01-01

    This paper looks at the technical, economic, environmental and regulatory barriers to the production of hydrogen from local wind resources in Sacramento, CA. Both central and distributed hydrogen generation are compared. The technical analysis uses 6 years of hourly wind data from Solano County to define the diurnal and seasonal wind resource. The impacts of a fluctuating power source on the electrolyzer are examined as well as the grid or hydrogen distribution and storage infrastructure constraints for implementation. An economic analysis comparing the price of hydrogen produced from the local wind resource is done with sensitivity analyses for capital and operating costs of both wind turbines and electrolyzers. In addition, the economic analysis includes considerations of increased demand for wind electricity by California utilities attempting to meet their Renewable Portfolio Standards. The environmental analysis compares the emissions reductions of CO 2 and criteria pollutants for different energy usage scenarios. These include comparing electricity and transportation emissions rates to optimize the use of wind energy and natural gas, as well as comparison of SULEV hybrid vehicles with FCV's and H 2 ICE's. Finally, an examination of the existing regulatory structure and policies that could prevent or encourage the use of wind to produce hydrogen in Sacramento is also included. (author)

  14. Fracture mechanics analysis and evaluation for the RPV of the Chinese Qinshan 300 MW NPP and PTS

    International Nuclear Information System (INIS)

    He Yinbiao; Isozaki, Toshikuni

    2000-03-01

    One of the most severe accident conditions of a reactor pressure vessel (RPV) in service is the loss of coolant accident (LOCA). Cold safety injection water is pumped into the downcomer of the RPV through inlet nozzles, while the internal pressure may remain at high level. Such an accident is called pressurized thermal shock (PTS) transient according to 10 CFR 50.61 definition. This paper illustrates the fracture mechanics analysis for the existing RPV of the Chinese Qinshan 300 MW nuclear power plant (NPP) under the postulated PTS transients that include SB-LOCA, LB-LOCA of Qinshan NPP and Rancho Seco transients. 3-D models with the flaw depth range a/w=0.05∼0.9 (a: flaw depth; w: wall thickness) were used to probe what kind of flaw and what kind of transient are most dangerous for the RPV in the end of life (EOF). Both the elastic and elastic-plastic material models were used in the stress analysis and fracture mechanics analysis. The different types of flaw and the influence of the stainless steel cladding on the fracture analysis were investigated for different PTS transients. comparing with the material initiation crack toughness K IC , the fracture evaluation for the RPV in question under PTS transients are performed in this paper. (author)

  15. Determinants of establishment survival for residential trees in Sacramento County, CA

    Science.gov (United States)

    Lara A. Roman; John J. Battles; Joe R. McBride

    2014-01-01

    Urban forests can provide ecosystem services that motivate tree planting campaigns, and tree survival is a key element of program success and projected benefits. We studied survival in a shade tree give-away program in Sacramento, CA, monitoring a cohort of young trees for five years on single-family residential properties. We used conditional inference trees to...

  16. 78 FR 5837 - Cancellation of Environmental Impact Statement/Environmental Impact Report on the Sacramento...

    Science.gov (United States)

    2013-01-28

    ... statewide economy. The SRWRS cost-sharing partners had identified their long-term needs for additional water... Sacramento were the cost-sharing partners. Reclamation published a notice of intent to prepare the EIS/EIR on...

  17. Final environmental assessment: Sacramento Energy Service Center

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    The Sacramento Area Office (SAO) of the Western Area Power Administration (Western) needs to increase the security of operations, to eliminate overcrowding at the current leased location of the existing facilities, to provide for future growth, to improve efficiency, and to reduce operating costs. The proposed action is to construct an approximate 40,000-square foot building and adjacent parking lot with a Solar Powered Electric Vehicle Charging Station installed to promote use of energy efficient transportation. As funding becomes available and technology develops, additional innovative energy-efficient measures will be incorporated into the building. For example the proposed construction of the Solar Powered Electric Vehicle Charging.

  18. Assessing the Performance of a Network of Low Cost Particulate Matter Sensors Deployed in Sacramento, California

    Science.gov (United States)

    Mukherjee, A. D.; Brown, S. G.; McCarthy, M. C.

    2017-12-01

    A new generation of low cost air quality sensors have the potential to provide valuable information on the spatial-temporal variability of air pollution - if the measurements have sufficient quality. This study examined the performance of a particulate matter sensor model, the AirBeam (HabitatMap Inc., Brooklyn, NY), over a three month period in the urban environment of Sacramento, California. Nineteen AirBeam sensors were deployed at a regulatory air monitoring site collocated with meteorology measurements and as a local network over an 80 km2 domain in Sacramento, CA. This study presents the methodology to evaluate the precision, accuracy, and reliability of the sensors over a range of meteorological and aerosol conditions. The sensors demonstrated a robust degree of precision during collocated measurement periods (R2 = 0.98 - 0.99) and a moderate degree of correlation against a Beta Attenuation Monitor PM2.5 monitor (R2 0.6). A normalization correction is applied during the study period so that each AirBeam sensor in the network reports a comparable value. The role of the meteorological environment on the accuracy of the sensor measurements is investigated, along with the possibility of improving the measurements through a meteorology weighted correction. The data quality of the network of sensors is examined, and the spatial variability of particulate matter through the study domain derived from the sensor network is presented.

  19. Application of MCNPX 2.7.D for reactor core management at the research reactor BR2

    International Nuclear Information System (INIS)

    Kalcheva, Silva; Koonen, Edgar

    2011-01-01

    The paper discusses application of the Monte Carlo burn up code MCNPX 2.7.D for whole core criticality and depletion analysis of the Material Testing Research Reactor BR2 at SCK-CEN in Mol, Belgium. Two different approaches in the use of MCNPX 2.7.D are presented. The first methodology couples the evolution of fuel depletion, evaluated by MCNPX 2.7.D in an infinite lattice with a steady-state 3-D power distribution in the full core model. The second method represents fully automatic whole core depletion and criticality calculations in the detailed 3-D heterogeneous geometry model of the BR2 reactor. The accuracy of the method and computational time as function of the number of used unique burn up materials in the model are being studied. The depletion capabilities of MCNPX 2.7.D are compared vs. the developed at the BR2 reactor department MCNPX & ORIGEN-S combined method. Testing of MCNPX 2.7.D on the criticality measurements at the BR2 reactor is presented. (author)

  20. Modeling of secondary emission processes in the negative ion based electrostatic accelerator of the International Thermonuclear Experimental Reactor

    OpenAIRE

    G. Fubiani; H. P. L. de Esch; A. Simonin; R. S. Hemsworth

    2008-01-01

    The negative ion electrostatic accelerator for the neutral beam injector of the International Thermonuclear Experimental Reactor (ITER) is designed to deliver a negative deuterium current of 40 A at 1 MeV. Inside the accelerator there are several types of interactions that may create secondary particles. The dominating process originates from the single and double stripping of the accelerated negative ion by collision with the residual molecular deuterium gas (≃29% losses). The resulting seco...

  1. Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

    International Nuclear Information System (INIS)

    Bonin, H.W.; Hilborn, J.W.; Carlin, G.E.; Gagnon, R.; Busatta, P.

    2014-01-01

    Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as 99 Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as 99 Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO 2 SO 4 ) with 994.2 g of 235 U (enrichment at 20%) providing an excess reactivity at operating temperature (40 o C) of 3.8 mk for a molality determined as 1.46 mol kg -1 for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 o C. Peak temperature and power were determined as 83 o C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the temperature and void coefficients are

  2. Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

    Energy Technology Data Exchange (ETDEWEB)

    Bonin, H.W., E-mail: bonin-h@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada); Hilborn, J.W. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Carlin, G.E. [Ontario Power Generation, Toronto, Ontario (Canada); Gagnon, R.; Busatta, P. [Canadian Forces (Canada)

    2014-07-01

    Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as {sup 99}Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as {sup 99}Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO{sub 2}SO{sub 4}) with 994.2 g of {sup 235}U (enrichment at 20%) providing an excess reactivity at operating temperature (40 {sup o}C) of 3.8 mk for a molality determined as 1.46 mol kg{sup -1} for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 {sup o}C. Peak temperature and power were determined as 83 {sup o}C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the

  3. Caracterización de las Diatomitas de Río Seco (Piura, Perú

    Directory of Open Access Journals (Sweden)

    Rodríguez Lichtenheldt, J.

    1998-10-01

    Full Text Available The occurrence of diatomites on the area of Rio Seco (Piura, Peru, has led the authors to study their physical, chemical and mineralogical properties with the aim to determinate their principal uses and applications. Conventional methods were applied besides of optical and electronical microscopy, difraction of X rays and thermal differential and gravimetric analysis. It is a medium quality material because of their silica and alumina contents, then the applications should be limited to fabrication of puzzolanic and ceramic materials for construction.

    La existencia de diatomita en la zona de Río Seco (Piura, Perú, ha llevado a los autores a realizar un estudio de sus propiedades físicas, químicas y mineralógicas, con el objeto de determinar sus principales usos y aplicaciones. Para ello se han utilizado las técnicas de análisis convencional, así como microscopia óptica y electrónica, difracción de rayos X y análisis térmico diferencial y gravimétrico. Tratándose de un material de calidad media, por los contenidos en sílice y alúmina que presenta, su aplicación quedaría restringida a la fabricación de materiales puzolánicos y cerámicos para la construcción.

  4. Core monitoring at the WNP-2 reactor

    International Nuclear Information System (INIS)

    Skeen, D.R.; Torres, R.H.; Burke, W.J.; Jenkins, I.; Jones, S.W.

    1992-01-01

    The WNP-2 reactor is a 3,323-MW(thermal) boiling water reactor (BWR) that is operated by the Washington Public Power Supply System. The WNP-2 reactor began commercial operation in 1984 and is currently in its eighth cycle. The core monitoring system used for the first cycle of operation was supplied by the reactor vendor. Cycles 2 through 6 were monitored with the POWERPLEX Core Monitoring Software System (CMSS) using the XTGBWR simulation code. In 1991, the supply system upgraded the core monitoring system by installing the POWERPLEX 2 CMSS prior to the seventh cycle of operation for WNP-2. The POWERPLEX 2 CMSS was developed by Siemens Power Corporation (SPC) and is based on SPC's advanced state-of-the-art reactor simulator code MICROBURN-B. The improvements in the POWERPLEX 2 system are possible as a result of advances in minicomputer hardware

  5. 75 FR 40726 - Revisions to the California State Implementation Plan, Sacramento Metropolitan Air Quality...

    Science.gov (United States)

    2010-07-14

    ... the California State Implementation Plan, Sacramento Metropolitan Air Quality Management District and South Coast Air Quality Management District AGENCY: Environmental Protection Agency (EPA). ACTION... Metropolitan Air Quality Management District (SMAQMD) and South Coast Air Quality Management District (SCAQMD...

  6. TA-2 Water Boiler Reactor Decommissioning Project

    International Nuclear Information System (INIS)

    Durbin, M.E.; Montoya, G.M.

    1991-06-01

    This final report addresses the Phase 2 decommissioning of the Water Boiler Reactor, biological shield, other components within the biological shield, and piping pits in the floor of the reactor building. External structures and underground piping associated with the gaseous effluent (stack) line from Technical Area 2 (TA-2) Water Boiler Reactor were removed in 1985--1986 as Phase 1 of reactor decommissioning. The cost of Phase 2 was approximately $623K. The decommissioning operation produced 173 m 3 of low-level solid radioactive waste and 35 m 3 of mixed waste. 15 refs., 25 figs., 3 tabs

  7. Preliminary Evaluation of Removing Used Nuclear Fuel from Shutdown Sites

    Energy Technology Data Exchange (ETDEWEB)

    Maheras, Steven J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Best, Ralph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ross, Steven B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Buxton, Kenneth A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); England, Jeffery L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McConnell, Paul E. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Massaro, Lawrence M. [Fermi Research Alliance (FRA), Batavia, IL (United States); Jensen, Philip J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-09-30

    A preliminary evaluation of removing spent nuclear fuel (SNF) from 13 shutdown nuclear power plant sites was performed. At these shutdown sites the nuclear power reactors have been permanently shut down and the sites have been decommissioned or are undergoing decommissioning. The shutdown sites were Maine Yankee, Yankee Rowe, Connecticut Yankee, Humboldt Bay, Big Rock Point, Rancho Seco, Trojan, La Crosse, Zion, Crystal River, Kewaunee, San Onofre, and Vermont Yankee. The evaluation was divided into four components: Characterization of the SNF and greater-than-Class C low-level radioactive waste (GTCC waste) inventory A description of the on-site infrastructure at the shutdown sites An evaluation of the near-site transportation infrastructure and transportation experience at the shutdown sites An evaluation of the actions necessary to prepare for and remove SNF and GTCC waste. The primary sources for the inventory of SNF and GTCC waste were the U.S. Department of Energy (DOE) spent nuclear fuel inventory database, industry publications such as StoreFUEL, and government sources such as the U.S. Nuclear Regulatory Commission. The primary sources for information on the conditions of on-site infrastructure and near-site transportation infrastructure and experience included information collected during site visits, information provided by managers at the shutdown sites, Facility Interface Data Sheets compiled for DOE in 2005, Services Planning Documents prepared for DOE in 1993 and 1994, industry publications such as Radwaste Solutions, and Google Earth. State staff, State Regional Group representatives, a Tribal representative, and a Federal Railroad Administration representative have participated in nine of the shutdown site visits. Every shutdown site was found to have at least one off-site transportation mode option for removing its SNF and GTCC waste; some have multiple options. Experience removing large components during reactor decommissioning provided an

  8. EBR-2 [Experimental Breeder Reactor-2] test programs

    International Nuclear Information System (INIS)

    Sackett, J.I.; Lehto, W.K.; Lindsay, R.W.; Planchon, H.P.; Lambert, J.D.B.; Hill, D.J.

    1990-01-01

    The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development, (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development, advanced control system development, plant diagnostics development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs

  9. Observations of the temperature dependent response of ozone to NOx reductions in the Sacramento, CA urban plume

    Science.gov (United States)

    Lafranchi, B. W.; Goldstein, A. H.; Cohen, R. C.

    2011-07-01

    Observations of NOx in the Sacramento, CA region show that mixing ratios decreased by 30 % between 2001 and 2008. Here we use an observation-based method to quantify net ozone (O3) production rates in the outflow from the Sacramento metropolitan region and examine the O3 decrease resulting from reductions in NOx emissions. This observational method does not rely on assumptions about detailed chemistry of ozone production, rather it is an independent means to verify and test these assumptions. We use an instantaneous steady-state model as well as a detailed 1-D plume model to aid in interpretation of the ozone production inferred from observations. In agreement with the models, the observations show that early in the plume, the NOx dependence for Ox (Ox = O3 + NO2) production is strongly coupled with temperature, suggesting that temperature-dependent biogenic VOC emissions and other temperature-related effects can drive Ox production between NOx-limited and NOx-suppressed regimes. As a result, NOx reductions were found to be most effective at higher temperatures over the 7 year period. We show that violations of the California 1-h O3 standard (90 ppb) in the region have been decreasing linearly with decreases in NOx (at a given temperature) and predict that reductions of NOx concentrations (and presumably emissions) by an additional 30 % (relative to 2007 levels) will eliminate violations of the state 1 h standard in the region. If current trends continue, a 30 % decrease in NOx is expected by 2012, and an end to violations of the 1 h standard in the Sacramento region appears to be imminent.

  10. McClellan Nuclear Radiation Center (MNRC) TRIGA reactor: The national organization of test research and training reactors

    International Nuclear Information System (INIS)

    Kiger, Kevin M.

    1994-01-01

    This year's TRTR conference is being hosted by the McClellan Nuclear Radiation Center. The conference will be held at the Red Lion Hotel in Sacramento, CA. The conference dates are scheduled for October 11-14, 1994. Deadlines for sponsorship commitment and papers have not been set, but are forthcoming. The newly remodeled Red Lion Hotel provides up-to-date conference facilities and one of the most desirable locations for dining, shopping and entertainment in the Sacramento area. While attendees are busy with the conference activities, a spouses program will be available. Although the agenda has not been set, the Sacramento area offers outings to San Francisco, Pier 39, Ghirardelli Square (famous for their chocolate), and a chance to discover 'El Dorado' in the gold country. Not to forget our own bit of history with visits to 'Old Sacramento and Old Folsom', where antiquities abound, to the world renown train museum and incredible eating establishments. (author)

  11. DOJ News Release: Local Contractor Pleads Guilty To Defrauding City Of Sacramento Of Stimulus Funds

    Science.gov (United States)

    SACRAMENTO, Calif. — US Attorney Benjamin B. Wagner announced today that Peter Scott, President of Advantage Demolition and Engineering (ADE), 47, of Roseville, pleaded guilty today to two counts of submitting false contractor bonds.

  12. NORTH SOLDIERS IN SOUTHERN WARS: THE MILITARY RECRUITMENT IN BAHIA AND PERNAMBUCO TO THE COLONY OF THE SACRAMENTO

    Directory of Open Access Journals (Sweden)

    Paulo César Possamai

    2011-06-01

    Full Text Available The North of the State of Brazil contributed to the creation and defense of Colonia do Sacramento. This article will address the military conscription in the Northern provinces, especially in Bahia and Pernambuco during the Eighteenth Century. We will give emphasis to the period of the siege from 1735 to 1737, when a large conscription was enforced in Portugal and in many Brazilian provinces in order to avoid the conquest of Sacramento by the Spaniards, as well as to strengthen Rio Grande de São Pedro, from which few men could return home.

  13. Presencia de hongos micorrízicos arbusculares (HMA en especies representativas del bosque seco tropical del litoral ecuatoriano

    Directory of Open Access Journals (Sweden)

    Ivette Chiquito Noboa

    2018-02-01

    Full Text Available Los hongos micorrízicos arbusculares (HMA son microorganismos que mantienen una relación simbiótica mutualista con las raíces de las plantas. El bosque seco tropical contiene abundantes especies de interés silvícola, sin embargo, en Ecuador se desconoce las relaciones simbióticas de los HMA con los árboles que representan el bosque seco. El propósito de este estudio fue aislar e identificar la presencia de HMA en determinadas especies vegetales de este nicho ecológico del Ecuador. Las muestras de suelo y raíces se recolectaron en la época húmeda entre los meses de marzo y abril del 2017. Los porcentajes de micorrización encontrados fueron los siguientes: Cochlospermun vitifolium (Bototillo 80.8%, Triplaris cumingiana (Fernán Sánchez 71.7%, Albizia multiflora (Compoño 70.0%, Tecoma castanifolia (Moyuyo de montaña 68.6%, Bursera graveolens (Palo Santo 68.3%, Sapindus saponaria (Jaboncillo 67.5%, Croton wagneri (Purga 65.0%, Ceiba trichistandra (Ceibo 62.2%. Todas las plantas muestreadas presentaron una densidad media de esporas por 100 gr de suelo, pero Triplaris cumingiana (Fernán Sánchez obtuvo una mayor esporulación a pesar de presentar la misma densidad media.

  14. Adaptive Management Methods to Protect the California Sacramento-San Joaquin Delta Water Resource

    Science.gov (United States)

    Bubenheim, David

    2016-01-01

    The California Sacramento-San Joaquin River Delta is the hub for California's water supply, conveying water from Northern to Southern California agriculture and communities while supporting important ecosystem services, agriculture, and communities in the Delta. Changes in climate, long-term drought, water quality changes, and expansion of invasive aquatic plants threatens ecosystems, impedes ecosystem restoration, and is economically, environmentally, and sociologically detrimental to the San Francisco Bay/California Delta complex. NASA Ames Research Center and the USDA-ARS partnered with the State of California and local governments to develop science-based, adaptive-management strategies for the Sacramento-San Joaquin Delta. The project combines science, operations, and economics related to integrated management scenarios for aquatic weeds to help land and waterway managers make science-informed decisions regarding management and outcomes. The team provides a comprehensive understanding of agricultural and urban land use in the Delta and the major water sheds (San Joaquin/Sacramento) supplying the Delta and interaction with drought and climate impacts on the environment, water quality, and weed growth. The team recommends conservation and modified land-use practices and aids local Delta stakeholders in developing management strategies. New remote sensing tools have been developed to enhance ability to assess conditions, inform decision support tools, and monitor management practices. Science gaps in understanding how native and invasive plants respond to altered environmental conditions are being filled and provide critical biological response parameters for Delta-SWAT simulation modeling. Operational agencies such as the California Department of Boating and Waterways provide testing and act as initial adopter of decision support tools. Methods developed by the project can become routine land and water management tools in complex river delta systems.

  15. Hyperkyphotic posture and risk of injurious falls in older persons: the Rancho Bernardo Study.

    Science.gov (United States)

    Kado, Deborah M; Huang, Mei-Hua; Nguyen, Claude B; Barrett-Connor, Elizabeth; Greendale, Gail A

    2007-06-01

    Falls among older adults can have serious physical and emotional consequences, ultimately leading to a loss of independence. Improved identification of those at risk for falls could lead to effective interventions. Because hyperkyphotic posture is associated with impaired physical functioning, we hypothesized that kyphosis may also be associated with falls. Participants were 1883 older adults from the Rancho Bernardo Study. Between 1988 and 1991, kyphosis was measured using a system of 1.7-cm blocks placed under the participants' heads if they were unable to lie flat without neck hyperextension. Data on falls including injurious falls, demographics, health, and habits were obtained from a self-administered questionnaire completed at the same visit. Hyperkyphosis was defined as requiring the use of > or = 1 blocks (n = 595, 31.6%). In this cohort, men were more likely to be hyperkyphotic than were women (p fall (p =.015). Those who fell were older, more likely to be women, had lower body mass index, did not exercise, did not drink alcohol, and had poor self-reported physical and emotional health. In age- and sex-adjusted models, those with hyperkyphosis were at 1.38-fold increased odds of experiencing an injurious fall (95% confidence interval [CI], 1.05-1.91; p =.02) that increased to 1.48 using a cutoff of > or = 2 blocks versus fall, after adjustment for possible confounders, men with moderate hyperkyphosis were at greatest fall risk. Moderate hyperkyphotic posture may signify an easily identifiable independent risk factor for injurious falls in older men, with the association being less pronounced in older women.

  16. 76 FR 20368 - Llano Seco Riparian Sanctuary Unit Restoration and Pumping Plant/Fish Screen Facility Protection...

    Science.gov (United States)

    2011-04-12

    ... Leader, Sacramento National Wildlife Refuge Complex, U.S. Fish and Wildlife Service, 752 County Road 99W... old and eroding, it plays a key role in protecting the PCGID-PID pumping plant. As the bank erodes... interdisciplinary team began studies to examine measures to protect the PCGID-PID pumping plant and fish screen...

  17. BR2 Reactor: Irradiation of fuels

    International Nuclear Information System (INIS)

    Verwimp, A.

    2005-01-01

    Safe, reliable and economical operation of reactor fuels, both UO 2 and MOX types, requires in-pile testing and qualification up to high target burn-up levels. In-pile testing of advanced fuels for improved performance is also mandatory. The objectives of research performed at SCK-CEN are to perform Neutron irradiation of LWR (Light Water Reactor) fuels in the BR2 reactor under relevant operating and monitoring conditions, as specified by the experimenter's requirements and to improve the on-line measurements on the fuel rods themselves

  18. Composição química do óleo fixo obtido dos frutos secos da [Chamomilla recutita (L. Rauschert] produzida no município de Mandirituba, PR.

    Directory of Open Access Journals (Sweden)

    N.P. Pereira

    Full Text Available A camomila [Chamomilla recutita (L. Rauschert], é uma planta empregada na indústria de medicamentos, cosméticos e alimentos. Os frutos secos da camomila conhecidos por "sementes" são provenientes dos capítulos florais, dos quais pode-se extrair um óleo fixo rico em ácidos graxos insaturados. Através da técnica de extração com hexano em dispositivo de soxhlet, foi obtido o óleo bruto dos frutos secos da camomila em 19% de rendimento. O óleo foi caracterizado pela técnica de CG-EM, revelando um elevado teor de ácido linoleico na sua composição. Portanto, o óleo oriundo dos frutos secos da camomila vem a ser uma matéria-prima potencialmente útil na dermo-farmácia.

  19. Peepo: inodoro seco para países en vías de desarrollo

    OpenAIRE

    Gómez Tuya, Alejandra

    2017-01-01

    Peepo es un inodoro seco para países en vías de desarrollo y situaciones de emergencia. Es un objeto que pretende enmarcarse en un programa de educación sobre la higiene para prevenir todos los problemas derivados de los malos hábitos, convirtiendo como incentivo un desecho (las heces y la orina) en recurso, los fertilizantes. Departamento de Teoría de la Arquitectura y Proyectos Arquitectónicos Grado en Ingeniería en Diseño Industrial y Desarrollo de Producto

  20. Optimism and Mortality in Older Men and Women: The Rancho Bernardo Study

    Directory of Open Access Journals (Sweden)

    Ericha G. Anthony

    2016-01-01

    Full Text Available Purpose. To examine the associations of optimism and pessimism with all-cause, cardiovascular disease (CVD, coronary heart disease (CHD, and cancer mortality in a population-based sample of older men and women followed ≤12 years. Methods. 367 men and 509 women aged ≥50 from the Rancho Bernardo Study attended a 1999–2002 research clinic visit when demographic, behavioral, and medical history were obtained and completed a 1999 mailed survey including the Life Orientation Test-Revised (LOT-R. Mortality outcomes were followed through 2012. Results. Average age at baseline was 74.1 years; during follow-up (mean = 8.1 years, 198 participants died, 62 from CVD, 22 from CHD, and 49 from cancer. Total LOT-R, optimism and pessimism scores were calculated. Participants with the highest optimism were younger and reported less alcohol use and smoking and more exercise. Cox proportional hazard models showed that higher total LOT-R and optimism, but not pessimism scores, were associated with reduced odds of CHD mortality after adjusting for age, sex, alcohol, smoking, obesity, physical exercise, and medication (HR = 0.86, 95% CI = 0.75, 0.99; HR = 0.77, 95% CI = 0.61, 0.99, resp.. No associations were found for all-cause, CVD, or cancer mortality. Conclusions. Optimism was associated with reduced CHD mortality in older men and women. The association of positive attitudes with mortality merits further study.

  1. Ageing management of the BR2 research reactor

    International Nuclear Information System (INIS)

    Verpoortem, J. R.; Van Dyck, S.

    2014-01-01

    At the Belgian nuclear research centre (SCK.CEN) several test reactors are operated. Among these, Belgian Reactor 2 (BR2) is the largest Material Test Reactor (MTR). This water-cooled, beryllium moderated reactor with a maximum thermal power of 100 MW became operational in 1962. Except for two major refurbishment campaigns of one year each, this reactor has been operated continuously over the past 50 years, with a frequency of 5-12 cycles per year. At present, BR2 is used for different research activities, the production of medical isotopes, the production of n-doped silicon and various training and education activities. (Author)

  2. 77 FR 47536 - Revisions to the California State Implementation Plan, Mojave Desert, Northern Sierra, Sacramento...

    Science.gov (United States)

    2012-08-09

    ... San Diego Air Pollution Agencies AGENCY: Environmental Protection Agency (EPA). ACTION: Direct final...), Sacramento Metropolitan Air Quality Management District (SMAQMD) and San Diego County Air Pollution Control...) September 2008, 5. ``Control Techniques Guidelines for Miscellaneous Metal and Plastic Parts Coatings,'' EPA...

  3. Reactor theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

    International Nuclear Information System (INIS)

    Henry, A.F.

    1980-01-01

    Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

  4. Local-scale invasion pathways and small founder numbers in introduced Sacramento pikeminnow (Ptychocheilus grandis)

    Science.gov (United States)

    Andrew P. Kinziger; Rodney J. Nakamoto; Bret C. Harvey

    2014-01-01

    Given the general pattern of invasions with severe ecological consequences commonly resulting from multiple introductions of large numbers of individuals on the intercontinental scale, we explored an example of a highly successful, ecologically significant invader introduced over a short distance, possibly via minimal propagule pressure. The Sacramento pikeminnow (

  5. DETERMINATION OF A MATHEMATICAL MODEL TO ESTIMATE THE AREA AND DRY WEIGHT OF THE LEAF LIMBO OF Prunus persica CV. Jarillo DETERMINACIÓN DE UN MODELO MATEMÁTICO PARA LA ESTIMACIÓN DEL ÁREA FOLIAR Y PESO SECO DEL LIMBO DE Prunus persica CV. Jarillo

    Directory of Open Access Journals (Sweden)

    Enrique Quevedo García

    2012-06-01

    Full Text Available Abstract. A study was conducted to determine the variables that estimated the leaf limbo area and the leaf limbo dry weight of peach Prunus persica (L. Batsch cv. Jarillo. Fifty leaves, aged 2.5 months, were selected and measured: leaf limbo length and width, petiole length, leaf length, petiole diameter, leaf limbo fresh weight, petiole fresh weight, leaf fresh weight, leaf limbo dry weight, petiole dry weight, leaf dry weight, length/width limbo, petiole length/limbo length and leaf limbo area. The results allowed to obtain regression equations for estimating the leaf area and the limbo dry weight. Using the lineal models LA = b1 + b2 (LLL x LLW and LA= b1+ b2LLL + b3LLW a leaf area equation was determined. Alternative models to calculate limbo dry weight were evaluated LLDW = -b1+ b2 LLFW and LLDW= - b1 + b2LLL + b3PL. The best equations found with an R2 of 0.99 were LA = 1.572 + 0.65169(LLL x LLW, LA=-23.106+2.8064LLW + 3.6761LLL and LLDW = -0.002+0.401(LLFW.Resumen. Se realizó un estudio para determinar las variables que estimaran el área del limbo foliar y el peso seco del limbo de durazno Prunus persica (L. Batsch cv. Jarillo. Se seleccionaron cincuenta hojas con 2,5 meses de edad, fueron medidos: ancho del limbo, longitud del limbo, longitud del peciolo, longitud hoja, diámetro peciolo, peso fresco del limbo, peso fresco del peciolo, peso fresco de la hoja, peso seco del limbo, peso seco peciolo, peso seco de la hoja, longitud /ancho limbo, longitud del peciolo/longitud del limbo, área foliar del limbo. Los resultados alcanzados permitieron obtener ecuaciones de regresión para estimar el área foliar del limbo y el peso seco del limbo. Se halló una ecuación para la determinación del área foliar del limbo con los modelos lineales LA = b1 + b2 (LLL x LLW y LA= b1 + b2LLL + b3LLW. También se evaluaron modelos alternativas para calcular el peso seco del limbo, LLDW = -b1+ b2LLFW y LLDW= - b1 + b2LLL + b3PL. Las mejores ecuaciones

  6. Katrina's Lessons in California: Social and Political Trajectories of Flood Management in the Sacramento River Watershed since 2005

    Science.gov (United States)

    Comby, E.; Le Lay, Y. F.; Piegay, H.

    2017-12-01

    Over the last decade, major changes have occurred in the way that environments are managed. They can be linked with external or internal events which may shape public perception. An external event can reveal a forgotten risk and create a social problem (Hilgartner et Bosk 1988). Following the Advocacy Coalition Framework (Sabatier 1988), we studied the role of Hurricane Katrina in flood management in California from 2005 to 2013. How do policies intend to increase the city's resilience? We compared different flood policies of the Sacramento River from 2005 to 2013, by combining field observations with a principal dataset of 340 regional newspaper items (Sacramento Bee). Media coverage was analyzed using content, quotation, and textometry as well as GIS. We underlined temporal variability in public perceptions towards floods. Some planning choices (such as levees) became controversial, while journalists praised weirs, bypasses, and dams. However, Katrina does not seem to have a real impact on urban sprawl strategies in three Sacramento neighborhoods (Fig.1). We analyzed also the limits of the comparison between New Orleans and Sacramento. Dialog between stakeholders existed in space and time between here (California) and elsewhere (Louisiana), present (post-2005) and past (Katrina catastrophe), and risk and disaster. Katrina was a national scandal with political announcements. However, flood policy was developed first at a regional and then local scales. After Katrina awareness, conflicts appear: some California residents refuse to have a policy linked to Katrina applied to them. We underlined that different stakeholders became prominent: it may be useless to tackle with only one institution. Some institutions had an integrated river management, while others kept a traditional risk management. We assessed the changes in river management while using discourse to understand the (potential) shift in human-river relationships from risk management to integrated river

  7. Groundwater Pumping and Streamflow in the Yuba Basin, Sacramento Valley, California

    Science.gov (United States)

    Moss, D. R.; Fogg, G. E.; Wallender, W. W.

    2011-12-01

    Water transfers during drought in California's Sacramento Valley can lead to increased groundwater pumping, and as yet unknown effects on stream baseflow. Two existing groundwater models of the greater Sacramento Valley together with localized, monitoring of groundwater level fluctuations adjacent to the Bear, Feather, and Yuba Rivers, indicate cause and effect relations between the pumping and streamflow. The models are the Central Valley Hydrologic Model (CVHM) developed by the U.S. Geological Survey and C2VSIM developed by Department of Water Resources. Using two models which have similar complexity and data but differing approaches to the agricultural water boundary condition illuminates both the water budget and its uncertainty. Water budget and flux data for localized areas can be obtained from the models allowing for parameters such as precipitation, irrigation recharge, and streamflow to be compared to pumping on different temporal scales. Continuous groundwater level measurements at nested, near-stream piezometers show seasonal variations in streamflow and groundwater levels as well as the timing and magnitude of recharge and pumping. Preliminary results indicate that during years with relatively wet conditions 65 - 70% of the surface recharge for the groundwater system comes from irrigation and precipitation and 30 - 35% comes from streamflow losses. The models further indicate that during years with relatively dry conditions, 55 - 60% of the surface recharge for the groundwater system comes from irrigation and precipitation while 40 - 45% comes from streamflow losses. The models irrigation water demand, surface-water and groundwater supply, and deep percolation are integrated producing values for irrigation pumping. Groundwater extractions during the growing season, approximately between April and October, increase by almost 200%. The effects of increased pumping seasonally are not readily evident in stream stage measurements. However, during dry time

  8. Interacciones entre semillas y escarabajos del estiércol (scarabaeinae) en un bosque tropical seco

    OpenAIRE

    Julissa Ocampo-Castillo; Ellen Andresen

    2018-01-01

    Los escarabajos del estiércol (Scarabaeinae) son insectos importantes en muchos ecosistemas terrestres por susfunciones ecológicas, derivadas del comportamiento de remover las heces de vertebrados. Este grupo de insectoses particularmente abundante en los bosques tropicales (BT). Sus funciones ecológicas han sido principalmenteestudiadas en los BT húmedos, existiendo poca información para los BT secos. Se realizaron experimentos de campoen la Estación de Biología de Chamela (Jalisco, México) ...

  9. BR2 reactor neutron beams

    International Nuclear Information System (INIS)

    Neve de Mevergnies, M.

    1977-01-01

    The use of reactor neutron beams is becoming increasingly more widespread for the study of some properties of condensed matter. It is mainly due to the unique properties of the ''thermal'' neutrons as regards wavelength, energy, magnetic moment and overall favorable ratio of scattering to absorption cross-sections. Besides these fundamental reasons, the impetus for using neutrons is also due to the existence of powerful research reactors (such as BR2) built mainly for nuclear engineering programs, but where a number of intense neutron beams are available at marginal cost. A brief introduction to the production of suitable neutron beams from a reactor is given. (author)

  10. Fission product release from SLOWPOKE-2 reactors

    Energy Technology Data Exchange (ETDEWEB)

    Harnden-Gillis, A M.C. [Queen` s Univ., Kingston, ON (Canada). Dept. of Physics

    1994-12-31

    Increasing radiation fields at several SLOWPOKE-2 reactors fuelled with highly enriched uranium aluminum alloy fuel have begun to interfere with the daily operation of these reactors. To investigate this phenomenon, samples of reactor container water and gas from the headspace were obtained at four SLOWPOKE-2 reactor facilities and examined by gamma ray spectroscopy methods. These radiation fields are due to the circulation of fission products within the reactor container vessel. The most likely source of the fission product release is an area of uranium-bearing material exposed to the coolant at the end weld line which originated at the time of fuel fabrication. The results of this study are compared with observations from an underwater visual examination of one core and the metallographic examination of archived fuel elements. 19 refs., 4 tabs., 8 figs.

  11. Climate Change and Flood Operations in the Sacramento Basin, California

    Directory of Open Access Journals (Sweden)

    Ann D. Willis

    2011-07-01

    Full Text Available Ann D. Willis, Jay R. Lund, Edwin S. Townsley, and Beth A. Faberdoi: http://dx.doi.org/10.15447/sfews.2014v9iss2art3Climate warming is likely to challenge many current conceptions and regulatory policies, particularly for water management. A warmer climate is likely to hinder flood operations in California’s Sacramento Valley by decreasing snowpack storage and increasing the rain fraction of major storms. This work examines how a warmer climate would change flood peaks and volumes for nine major historical floods entering Shasta, Oroville, and New Bullards Bar reservoirs, using current flood flow forecast models and current flood operating rules. Shasta and Oroville have dynamic flood operation curves that accommodate many climate-warming scenarios. New Bullards Bar’s more static operating rule performs poorly for these conditions. Revisiting flood operating rules is an important adaptation for climate warming.

  12. Avaliação da qualidade de tomate seco em conserva Evaluation of quality of dried tomato

    Directory of Open Access Journals (Sweden)

    Gisele A. Camargo

    2007-10-01

    Full Text Available O tomate seco em conserva é alvo de crescente aceitação no mercado brasileiro; sua utilização é comum em aperitivos e na culinária como ingrediente de molhos e pizzas. Avaliou-se, neste trabalho o efeito dos seguintes fatores na qualidade do tomate seco: variedade de tomate (Rio Grande e Débora Plus, geometria de corte (pedaços de ½ e ¼ com relação ao eixo maior do fruto, presença ou ausência de sementes e teor de umidade final (25 e 35%, mediante análises instrumentais de cor e textura e testes sensoriais afetivos. Os resultados mostraram que a variedade Rio Grande apresentou melhor mastigabilidade e dureza, porém maior suscetibilidade ao escurecimento após o processo de secagem. De forma geral, a preferência dos consumidores foi por tomates secos com 35% de umidade final, enquanto a melhor qualidade final foi obtida a partir do tratamento com a variedade Rio Grande e umidade final de 35%.Preserved dried tomato has been gaining increasing acceptance in the Brazilian market, its use being common in appetizers and also in the cooking, as an ingredient of sauces and pizzas. The effect of the following factors on the quality of dried tomato was evaluated: variety of tomato (Rio Grande and Débora Plus, geometry of pieces (½ and ¼ to the fruit major axis, presence or absence of seeds and final moisture content (25 and 35% by means of instrumental texture, and color analysis and sensorial affective tests. The results showed that the variety Rio Grande presented better physical parameters but was more susceptible to darkness. Generally, the consumers preferred dried tomatoes at 35% moisture content. The best final quality of dried tomato was obtained from the treatment performed with Rio Grande variety and 35% final moisture content.

  13. Pressurized water reactor simulator. Workshop material. 2. ed

    International Nuclear Information System (INIS)

    2005-01-01

    The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development. And the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 reactor department simulator from the Moscow Engineering and Physics Institute, the Russian Federation is presented in the IAEA Training Course Series No. 21, 2nd edition, 'WWER-1000 Reactor Simulator' (2005). Course material for workshops using a boiling water reactor simulator developed for the IAEA by Cassiopeia Technologies Incorporated of Canada (CTI) is presented in the IAEA publication: Training Course Series No.23, 2nd edition, 'Boiling Water Reactor Simulator' (2005). This report consists of course material for workshops using a pressurized water reactor simulator

  14. Fine-scale habitat preference of green sturgeon (Acipenser medirostris) within three spawning locations in the Sacramento River, California

    Science.gov (United States)

    Wyman, Megan T.; Thomas, Michael J.; McDonald, Richard R.; Hearn, Alexander R.; Battleson, Ryan D.; Chapman, Eric D.; Kinzel, Paul J.; Minear, J. Tobey; Mora, Ethan A.; Nelson, Jonathan M.; Pagel, Matthew D.; Klimley, A. Peter

    2018-01-01

    Vast sections of the Sacramento River have been listed as critical habitat by the National Marine Fisheries Service for green sturgeon spawning (Acipenser medirostris), yet spawning is known to occur at only a few specific locations. This study reveals the range of physical habitat variables selected by adult green sturgeon during their spawning period. We integrated fine-scale fish positions, physical habitat characteristics, discharge, bathymetry, and simulated velocity and depth using a 2-dimensional hydraulic model (FaSTMECH). The objective was to create habitat suitability curves for depth, velocity, and substrate type within three known spawning locations over two years. An overall cumulative habitat suitability score was calculated that averaged the depth, velocity, and substrate scores over all fish, sites, and years. A weighted usable area (WUA) index was calculated throughout the sampling periods for each of the three sites. Cumulative results indicate that the microhabitat characteristics most preferred by green sturgeon in these three spawning locations were velocities between 1.0-1.1 m/s, depths of 8-9 m, and gravel and sand substrate. This study provides guidance for those who may in the future want to increase spawning habitat for green sturgeon within the Sacramento River.

  15. Prevalence and risk factors For vitamin D deficiency among healthy infants in Sacramento, California

    Science.gov (United States)

    Objective: The purpose of this study was to assess the vitamin D status of healthy infants 6-18 months of age in Sacramento, CA. Patients and Methods: This was a one-year, cross-sectional study among a convenience sample of healthy infants seen at routine “well child” or follow-up appointments at t...

  16. Assessment of LED Technology in Ornamental Post-Top Luminaires (Host Site: Sacramento, CA)

    Energy Technology Data Exchange (ETDEWEB)

    Tuenge, Jason R.

    2011-12-01

    The DOE Municipal Solid-State Street Lighting Consortium has evaluated four different LED replacements for existing ornamental post-top street lights in Sacramento, California. The project team was composed of the City and its consultant, PNNL (representing the Consortium), and the Sacramento Municipal Utility District. Product selection was finalized in March 2011, yielding one complete luminaire replacement and three lamp-ballast retrofit kits. Computer simulations, field measurements, and laboratory testing were performed to compare the performance and cost-effectiveness of the LED products relative to the existing luminaire with 100 W high-pressure sodium lamp. After it was confirmed the LED products were not equivalent to HPS in terms of initial photopic illumination, the following parameters were scaled proportionally to enable equitable (albeit hypothetical) comparisons: light output, input wattage, and pricing. Four replacement scenarios were considered for each LED product, incorporating new IES guidance for mesopic multipliers and lumen maintenance extrapolation, but life cycle analysis indicated cost effectiveness was also unacceptable. Although LED efficacy and pricing continue to improve, this project serves as a timely and objective notice that LED technology may not be quite ready yet for such applications.

  17. Size and shape stasis in late Pleistocene mammals and birds from Rancho La Brea during the Last Glacial-Interglacial cycle

    Science.gov (United States)

    Prothero, Donald R.; Syverson, Valerie J.; Raymond, Kristina R.; Madan, Meena; Molina, Sarah; Fragomeni, Ashley; DeSantis, Sylvana; Sutyagina, Anastasiya; Gage, Gina L.

    2012-11-01

    Conventional neo-Darwinian theory views organisms as infinitely sensitive and responsive to their environments, and considers them able to readily change size or shape when they adapt to selective pressures. Yet since 1863 it has been well known that Pleistocene animals and plants do not show much morphological change or speciation in response to the glacial-interglacial climate cycles. We tested this hypothesis with all of the common birds (condors, golden and bald eagles, turkeys, caracaras) and mammals (dire wolves, saber-toothed cats, giant lions, horses, camels, bison, and ground sloths) from Rancho La Brea tar pits in Los Angeles, California, which preserves large samples of many bones from many well-dated pits spanning the 35,000 years of the Last Glacial-Interglacial cycle. Pollen evidence showed the climate changed from chaparral/oaks 35,000 years ago to snowy piñon-juniper forests at the peak glacial 20,000 years ago, then back to the modern chaparral since the glacial-interglacial transition. Based on Bergmann's rule, we would expect peak glacial specimens to have larger body sizes, and based on Allen's rule, peak glacial samples should have shorter and more robust limbs. Yet statistical analysis (ANOVA for parametric samples; Kruskal-Wallis test for non-parametric samples) showed that none of the Pleistocene pit samples is statistically distinct from the rest, indicating complete stasis from 35 ka to 9 ka. The sole exception was the Pit 13 sample of dire wolves (16 ka), which was significantly smaller than the rest, but this did not occur in response to climate change. We also performed a time series analysis of the pit samples. None showed directional change; all were either static or showed a random walk. Thus, the data show that birds and mammals at Rancho La Brea show complete stasis and were unresponsive to the major climate change that occurred at 20 ka, consistent with other studies of Pleistocene animals and plants. Most explanations for such

  18. Proceedings of the National Silviculture Workshop: Silviculture for All Resources; Sacramento, CA; May 11-14, 1987

    Science.gov (United States)

    Melanie Malespin Woolever; Mike Smith; Elizabeth McGraw; Mike Lanasa; Arthur C. Zack; Chris Reichert; Robert MacWhorter; Michael R. Lennartz; Richard A. Lancia; Marc G. Rounsaville; James R. Sedell; Fred H. Everest; David R. Gibbons; Stephen R. Shifley; Melinda Moeur; David A. Marquis; Richard O. Fitzgerald; Nelson Loftus; Thomas C. Turpin; William R. Terrill; Glenn L. Crouch; Wayne D. Shepperd; Edith W. Petrick; John J. Petrick; Roger W. Dennington; Allan W. Ashton; Hubertus J. Mittmann; Gary Thompson; Ken Sonksen; David A. Stark; Michael A. Ware; Allan J. West; Patrick D. Jackson; Richard L. Bassett; Jimmie D. Chew; William B. White; Bruce W. Morse; Mike Znerold; Russell T. Graham; Peyton W. Owston; Richard G. Miller; John R. Nesbitt; Gaston Porterie; Ernest Del Rio

    1987-01-01

    The 1987 National Silviculture Workshop was held in Sacramento, California, and the Eldorado National Forest. The purpose of the workshop was to discuss, review, and share information and experiences regarding how silviculture can serve as the tool to help accomplish the objectives of many resources.

  19. Advances in Reactor Physics, Mathematics and Computation. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    These proceedings of the international topical meeting on advances in reactor physics, mathematics and computation, Volume 2, are divided into 7 sessions bearing on: - session 7: Deterministic transport methods 1 (7 conferences), - session 8: Interpretation and analysis of reactor instrumentation (6 conferences), - session 9: High speed computing applied to reactor operations (5 conferences), - session 10: Diffusion theory and kinetics (7 conferences), - session 11: Fast reactor design, validation and operating experience (8 conferences), - session 12: Deterministic transport methods 2 (7 conferences), - session 13: Application of expert systems to physical aspects of reactor design and operation.

  20. Quantifying Activated Floodplains on a Lowland Regulated River: Its Application to Floodplain Restoration in the Sacramento Valley

    Directory of Open Access Journals (Sweden)

    Philip B. Williams

    2009-09-01

    Full Text Available We describe a process and methodology for quantifying the extent of a type of historically prevalent, but now relatively rare, ecologically-valuable floodplains in the Sacramento lowland river system: frequently-activated floodplains. We define a specific metric the “Floodplain Activation Flow” (FAF, which is the smallest flood pulse event that initiates substantial beneficial ecological processes when associated with floodplain inundation. The “Activated Floodplain” connected to the river is then determined by comparison of FAF stage with floodplain topography. This provides a simple definition of floodplain that can be used as a planning, goal setting, monitoring, and design tool by resource managers since the FAF event is the smallest flood and corresponding floodplain area with ecological functionality—and is necessarily also inundated in larger flood events, providing additional ecological functions. For the Sacramento River we selected a FAF definition to be the river stage that occurs in two out of three years for at least seven days in the mid-March to mid-May period and "Activated Floodplains" to be those lands inundated at that stage. We analyzed Activated Floodplain area for four representative reaches along the lower Sacramento River and the Yolo Bypass using stream gauge data. Three of the most significant conclusions are described: (1 The area of active functional floodplain is likely to be less than commonly assumed based on extent of riparian vegetation; (2 Levee setbacks may not increase the extent of this type of ecologically-productive floodplain without either hydrologic or topographic changes; (3 Within the Yolo Bypass, controlled releases through the Fremont Weir could maximize the benefits associated with Activated Floodplain without major reservoir re-operation or grading. This approach identifies a significant opportunity to integrate floodplain restoration with flood management by establishing a FAF stage

  1. Characterizing Flow and Suspended Sediment Trends in the Sacramento River Basin, CA Using Hydrologic Simulation Program - FORTRAN (HSPF)

    Science.gov (United States)

    Stern, M. A.; Flint, L. E.; Flint, A. L.; Wright, S. A.; Minear, J. T.

    2014-12-01

    A watershed model of the Sacramento River Basin, CA was developed to simulate streamflow and suspended sediment transport to the San Francisco Bay Delta (SFBD) for fifty years (1958-2008) using the Hydrological Simulation Program - FORTRAN (HSPF). To compensate for the large model domain and sparse data, rigorous meteorological development and characterization of hydraulic geometry were employed to spatially distribute climate and hydrologic processes in unmeasured locations. Parameterization techniques sought to include known spatial information for tributaries such as soil information and slope, and then parameters were scaled up or down during calibration to retain the spatial characteristics of the land surface in un-gaged areas. Accuracy was assessed by comparing model calibration to measured streamflow. Calibration and validation of the Sacramento River ranged from "good" to "very good" performance based upon a "goodness-of-fit" statistical guideline. Model calibration to measured sediment loads were underestimated on average by 39% for the Sacramento River, and model calibration to suspended sediment concentrations were underestimated on average by 22% for the Sacramento River. Sediment loads showed a slight decreasing trend from 1958-2008 and was significant (p < 0.0025) in the lower 50% of stream flows. Hypothetical climate change scenarios were developed using the Climate Assessment Tool (CAT). Several wet and dry scenarios coupled with temperature increases were imposed on the historical base conditions to evaluate sensitivity of streamflow and sediment on potential changes in climate. Wet scenarios showed an increase of 9.7 - 17.5% in streamflow, a 7.6 - 17.5% increase in runoff, and a 30 - 93% increase in sediment loads. The dry scenarios showed a roughly 5% decrease in flow and runoff, and a 16 - 18% decrease in sediment loads. The base hydrology was most sensitive to a temperature increase of 1.5 degrees Celsius and an increase in storm intensity and

  2. Effect of Climate Extremes, Seasonal Change, and Agronomic Practices on Measured Evapotranspiration and CO2 Exchange in Sacramento-San Joaquin River Delta Alfalfa Fields

    Science.gov (United States)

    Clay, J.; Kent, E. R.; Leinfelder-Miles, M.; Paw U, K. T.; Little, C.; Lambert, J. J.

    2017-12-01

    Evapotranspiration and CO2 exchange was measured in five alfalfa fields in the Sacramento-San Joaquin River Delta region from 2016 to 2017 using eddy covariance and surface renewal methods. Seasonal changes of evapotranspiration and CO2 fluxes were compared between 2016, a drought year, and 2017, a high rainfall year. Additionally, changes in evapotranspiration and CO2 flux were investigated across various agronomic considerations, such as irrigation methods (border-check flood and sub-surface), stand life, and herbicide programs. Components of the energy balance, including net radiation, latent heat, ground heat flux, and sensible heat, were evaluated considering correlations to wind speed measured by three sonic anemometers, irrigation frequency, and crop cutting cycle. Comparisons between two different types of radiometers were also carried out. Under drought conditions, we observed higher amounts of evapotranspiration in a field having a stand life of less than two years of age compared to older stands, and in a sub-surface irrigated field compared to flood irrigated fields.

  3. Seco-B-Ring Steroidal Dienynes with Aromatic D Ring: Design, Synthesis and Biological Evaluation

    Directory of Open Access Journals (Sweden)

    Marcin Szybinski

    2017-10-01

    Full Text Available Continuing our structure-activity studies on the vitamin D analogs with the altered intercyclic seco-B-ring fragment, we designed compounds possessing dienyne system conjugated with the benzene D ring. Analysis of the literature data and the docking experiments seemed to indicate that the target compounds could mimic the ligands with a good affinity to the vitamin D receptor (VDR. Multi-step synthesis of the C/D-ring building block of the tetralone structure was achieved and its enol triflate was coupled with the known A-ring fragments, possessing conjugated enyne moiety, using Sonogashira protocol. The structures of the final products were confirmed by NMR, UV and mass spectroscopy. Their binding affinities for the full-length human VDR were determined and it was established that compound substituted at C-2 with exomethylene group showed significant binding to the receptor. This analog was also able to induce monocytic differentiation of HL-60 cells.

  4. Ganoboninketals A-C, Antiplasmodial 3,4-seco-27-Norlanostane Triterpenes from Ganoderma boninense Pat.

    Science.gov (United States)

    Ma, Ke; Ren, Jinwei; Han, Junjie; Bao, Li; Li, Li; Yao, Yijian; Sun, Chen; Zhou, Bing; Liu, Hongwei

    2014-08-22

    Three new nortriterpenes, ganoboninketals A-C (1-3), featuring rearranged 3,4-seco-27-norlanostane skeletons and highly complex polycyclic systems were isolated from the medicinal mushroom Ganoderma boninense. The structures of the new metabolites were established by spectroscopic methods. The absolute configurations in 1-3 were assigned by electronic circular dichroism (ECD) calculations. Compounds 1-3 showed antiplasmodial activity against Plasmodium falciparum with IC50 values of 4.0, 7.9, and 1.7 μM, respectively. Compounds 1 and 3 also displayed weak cytotoxicity against A549 cell line with IC50 values of 47.6 and 35.8 μM, respectively. Compound 2 showed weak cytotoxicity toward HeLa cell line with an IC50 value of 65.5 μM. Compounds 1-3 also presented NO inhibitory activity in the LPS-induced macrophages with IC50 values of 98.3, 24.3, and 60.9 μM, respectively.

  5. Lista comentada de las plantas vasculares del enclave seco interandino de la tatacoa (huila, colombia)

    OpenAIRE

    FIGUEROA-C., YISELA; GALEANO, GLORIA

    2012-01-01

    Se presenta el inventario florístico del enclave seco interandino de La Tatacoa (vallede la parte alta del río Magdalena, Huila, Colombia). Se encontraron 223 especies,distribuidas en 170 géneros y 60 familias. A nivel florístico, la familia Leguminosaees la más diversificada con 36 especies y 28 géneros, seguida por Poaceae (20/15),Euphorbiaceae (13/6), Asteraceae (10/10) y Cactaceae (8/7). El hábito de crecimientopredominante en términos de riqueza de especies fue el de las hierbas, seguido...

  6. Revised Environmental Assessment for the Sacramento Area Office Western Area Power Administration, 1994 Power Marketing Plan

    International Nuclear Information System (INIS)

    1992-08-01

    This document presents information on power marketing; expiring contracts; economic methods and assumptions; detailed power supply cost data; guidelines and acceptance criteria for conservation and renewable energy projects; hourly flow impacts graphs; difference in hydro dispatch; generation data; flow data; fishery resources of the Sacramento River; and water quality

  7. Rationale for anti-inflammatory therapy in dry eye syndrome Bases da terapia antiinflamatória em síndrome do olho seco

    Directory of Open Access Journals (Sweden)

    CS De Paiva

    2008-12-01

    Full Text Available Dry eye is a multifactorial condition that results in a dysfunctional lacrimal functional unit. Evidence suggests that inflammation is involved in the pathogenesis of the disease. Changes in tear composition including increased cytokines, chemokines, metalloproteinases and the number of T cells in the conjunctiva are found in dry eye patients and in animal models. This inflammation is responsible in part for the irritation symptoms, ocular surface epithelial disease, and altered corneal epithelial barrier function in dry eye. There are several anti-inflammatory therapies for dry eye that target one or more of the inflammatory mediators/pathways that have been identified and are discussed in detail.Olho seco é uma doença multifatorial que resulta em disfunção da unidade lacrimal glandular. Evidências sugerem que inflamação está involvida na patogênese da doença. Mudanças na composição das lágrimas, incluindo aumento de citocinas, quimiocinas, metaloproteinases e o número de células T na conjuntiva são encontrados em pacientes com olho seco e em modelos animais. Esta inflamação é responsável em parte pelos sintomas de irritação, doença epitelial de surperfície ocular e função epitelial de barreira alterada em olho seco. Existem várias terapias antiinflamatórias que se direcionam para um ou mais mediadores/vias que foram identificados e são discutidos em detalhe.

  8. Neutron transport. Physics and calculation of nuclear reactors with applications to pressurized water reactors and fast neutron reactors. 2 ed.

    International Nuclear Information System (INIS)

    Bussac, J.; Reuss, P.

    1985-01-01

    This book presents the main physical bases of neutron theory and nuclear reactor calculation. 1) Interactions of neutrons with matter and basic principles of neutron transport; 2) Neutron transport in homogeneous medium and the neutron field: kinetic behaviour, slowing-down, resonance absorption, diffusion equation, processing methods; 3) Theory of a reactor constituted with homogeneous zones: critical condition, kinetics, separation of variables, calculation and neutron balance of the fundamental mode, one-group and multigroup theories; 4) Study of heterogeneous cell lattices: fast fission factor, resonance absorption, thermal output factor, diffusion coefficient, computer codes; 5) Operation and control of reactors: perturbation theory, reactivity, fuel properties evolution, poisoning by fission products, calculation of a reactor and fuel management; 6) Study of some types of reactors: PWR and fast breeder reactors, the main reactor types of the present French program [fr

  9. Ingeniería básica de una planta de gasificación de lodos de EDAR para el tratamiento de 14.000 Mg/año de lodo seco

    OpenAIRE

    Muniesa Bastida , Blanca

    2005-01-01

    Actualmente dos plantas de secado de fango de EDAR deshidratado (80% de humedad) gestionadas por la empresa SGT S.A. y localizadas una en el término municipal de Rubí y la otra en Mataró producen, conjuntamente, 14.000 Mg/año de fango seco (menos del 20% de humedad). El secado se realiza a partir de los gases de escape de unos motores que consumen gas natural. Se plantea la revalorización de este fango seco, que actualmente se conduce al vertedero como residuo, mediante un proc...

  10. TPDWR2: thermal power determination for Westinghouse reactors, Version 2. User's guide

    International Nuclear Information System (INIS)

    Kaczynski, G.M.; Woodruff, R.W.

    1985-12-01

    TPDWR2 is a computer program which was developed to determine the amount of thermal power generated by any Westinghouse nuclear power plant. From system conditions, TPDWR2 calculates enthalpies of water and steam and the power transferred to or from various components in the reactor coolant system and to or from the chemical and volume control system. From these results and assuming that the reactor core is operating at constant power and is at thermal equilibrium, TPDWR2 calculates the thermal power generated by the reactor core. TPDWR2 runs on the IBM PC and XT computers when IBM Personal Computer DOS, Version 2.00 or 2.10, and IBM Personal Computer Basic, Version D2.00 or D2.10, are stored on the same diskette with TPDWR2

  11. Once-through CANDU reactor models for the ORIGEN2 computer code

    International Nuclear Information System (INIS)

    Croff, A.G.; Bjerke, M.A.

    1980-11-01

    Reactor physics calculations have led to the development of two CANDU reactor models for the ORIGEN2 computer code. The model CANDUs are based on (1) the existing once-through fuel cycle with feed comprised of natural uranium and (2) a projected slightly enriched (1.2 wt % 235 U) fuel cycle. The reactor models are based on cross sections taken directly from the reactor physics codes. Descriptions of the reactor models, as well as values for the ORIGEN2 flux parameters THERM, RES, and FAST, are given

  12. The Sacramento-San Joaquin Delta Conflict: Strategic Insights for California's Policymakers

    Science.gov (United States)

    Moazezi, M. R.

    2013-12-01

    The Sacramento-San Joaquin Delta - a major water supply source in California and a unique habitat for many native and invasive species--is on the verge of collapse due to a prolonged conflict over how to manage the Delta. There is an urgent need to expedite the resolution of this conflict because the continuation of the status quo would leave irreversible environmental consequences for the entire state. In this paper a systematic technique is proposed for providing strategic insights into the Sacramento-San Joaquin Delta conflict. Game theory framework is chosen to systematically analyze behavioral characteristics of decision makers as well as their options in the conflict with respect to their preferences using a formal mathematical language. The Graph Model for Conflict Resolution (GMCR), a recent game-theoretic technique, is applied to model and analyze the Delta conflict in order to better understand the options, preferences, and behavioral characteristics of the major decision makers. GMCR II as a decision support system tool based on GMCR concept is used to facilitate the analysis of the problem through a range of non-cooperative game theoretic stability definitions. Furthermore, coalition analysis is conducted to analyze the potential for forming partial coalitions among decision makers, and to investigate how forming a coalition can influence the conflict resolution process. This contribution shows that involvement of the State of California is necessary for developing an environmental-friendly resolution for the Delta conflict. It also indicates that this resolution is only achievable through improving the fragile levee systems and constructing a new water export facility.

  13. Status of groundwater quality in the Southern, Middle, and Northern Sacramento Valley study units, 2005-08: California GAMA Priority Basin Project

    Science.gov (United States)

    Bennett, George L.; Fram, Miranda S.; Belitz, Kenneth

    2011-01-01

    Groundwater quality in the Southern, Middle, and Northern Sacramento Valley study units was investigated as part of the Priority Basin Project of the Groundwater Ambient Monitoring and Assessment (GAMA) Program. The study units are located in California's Central Valley and include parts of Butte, Colusa, Glenn, Placer, Sacramento, Shasta, Solano, Sutter, Tehama, Yolo, and Yuba Counties. The GAMA Priority Basin Project is being conducted by the California State Water Resources Control Board in collaboration with the U.S. Geological Survey and the Lawrence Livermore National Laboratory. The three study units were designated to provide spatially-unbiased assessments of the quality of untreated groundwater in three parts of the Central Valley hydrogeologic province, as well as to provide a statistically consistent basis for comparing water quality regionally and statewide. Samples were collected in 2005 (Southern Sacramento Valley), 2006 (Middle Sacramento Valley), and 2007-08 (Northern Sacramento Valley). The GAMA studies in the Southern, Middle, and Northern Sacramento Valley were designed to provide statistically robust assessments of the quality of untreated groundwater in the primary aquifer systems that are used for drinking-water supply. The assessments are based on water-quality data collected by the USGS from 235 wells in the three study units in 2005-08, and water-quality data from the California Department of Public Health (CDPH) database. The primary aquifer systems (hereinafter, referred to as primary aquifers) assessed in this study are defined by the depth intervals of the wells in the CDPH database for each study unit. The quality of groundwater in shallow or deep water-bearing zones may differ from quality of groundwater in the primary aquifers; shallow groundwater may be more vulnerable to contamination from the surface. The status of the current quality of the groundwater resource was assessed by using data from samples analyzed for volatile organic

  14. Radiation protection at the RA Reactor in 1988, Part -2, RA reactor annual report

    International Nuclear Information System (INIS)

    Ninkovic, M.; Ajdacic, N.; Zaric, M.; Vukovic, Z.

    1988-01-01

    Radiation protection tasks which enable safe operation of the RA reactor, and are defined according the the legal regulations and IAEA safety recommendations are sorted into four categories in this report: (1) Control of the working environment, dosimetry at the RA reactor and radiation protection; (2) Radioactivity control in the vicinity of the reactor and meteorology measurements; (3) Decontamination and relevant actions, collecting and treatment of fluid effluents; and and solid radioactive wastes [sr

  15. NOAA TIFF Image - .75m Multibeam Backscatter, US Virgin Islands - Vieques Island (El Seco) - Project NF-09-01 - (2009), UTM 20N WGS 84

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This dataset contains a GeoTIFF with .75x.75 meter cell size representing the backscatter or intensity of sound returned from the seafloor in "El Seco" east of...

  16. NOAA TIFF Image - 1m Multibeam Bathymetry, US Virgin Islands - Vieques Island (El Seco) - Project NF-09-01 - (2009), UTM 20N NAD83

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This dataset contains a unified ESRI Geotiff with 1x1 meter cell size representing the bathymetry of El Seco, a selected portion of seafloor east of Vieques Island,...

  17. Irradiation effects on Zr-2.5Nb in power reactors

    Energy Technology Data Exchange (ETDEWEB)

    Song, C., E-mail: Carol.Song@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

    2016-06-15

    Zirconium alloys are widely used as structural materials in nuclear applications because of their attractive properties such as a low absorption cross-section for thermal neutrons, excellent corrosion resistance in water, and good mechanical properties at reactor operating temperatures. Zr-2.5Nb is one of the most commonly used zirconium alloys and has been used for pressure tube materials in CANDU (Canada Deuterium Uranium) and RBMK (Reaktor Bolshoy Moshchnosti Kanalnyy, 'High Power Channel-type Reactor') reactors for over 40 years. In a recent report from the Electric Power Research Institute, Zr-2.5Nb was identified as one of the candidate materials for use in normal structural applications in light-water reactors owing to its increased resistance to irradiation-induced degradation as compared with currently used materials. Historically, the largest program of in-reactor tests on zirconium alloys was performed by Atomic Energy of Canada Limited. Over many years of in-reactor testing and CANDU operating experience with Zr- 2.5Nb, extensive research has been conducted on the irradiation effects on its microstructures, mechanical properties, deformation behaviours, fracture toughness, delayed hydride cracking, and corrosion. Most of the results on Zr-2.5Nb obtained from CANDU experience could be used to predict the material performance under light water reactors. This paper reviews the irradiation effects on Zr-2.5Nb in power reactors (including heavy-water and light-water reactors) and summarizes the current state of knowledge. (author)

  18. Spatial trends and impairment assessment of mercury in sport fish in the Sacramento-San Joaquin Delta watershed

    International Nuclear Information System (INIS)

    Melwani, A.R.; Bezalel, S.N.; Hunt, J.A.; Grenier, J.L.; Ichikawa, G.; Heim, W.; Bonnema, A.; Foe, C.; Slotton, D.G.; Davis, J.A.

    2009-01-01

    A three-year study was conducted to examine mercury in sport fish from the Sacramento-San Joaquin Delta. More than 4000 fish from 31 species were collected and analyzed for total mercury in individual muscle filets. Largemouth bass and striped bass were the most contaminated, averaging 0.40 μg/g, while redear sunfish, bluegill and rainbow trout exhibited the lowest (<0.15 μg/g) concentrations. Spatial variation in mercury was evaluated with an analysis of covariance model, which accounted for variability due to fish size and regional hydrology. Significant regional differences in mercury were apparent in size-standardized largemouth bass, with concentrations on the Cosumnes and Mokelumne rivers significantly higher than the central and western Delta. Significant prey-predator mercury correlations were also apparent, which may explain a significant proportion of the spatial variation in the watershed. - Regional differences in sport fish mercury were found in the Sacramento-San Joaquin Delta.

  19. Leafcutter bee nests and pupae from the Rancho La Brea Tar Pits of Southern California: implications for understanding the paleoenvironment of the Late Pleistocene.

    Directory of Open Access Journals (Sweden)

    Anna R Holden

    Full Text Available The Rancho La Brea Tar Pits is the world's richest and most important Late Pleistocene fossil locality and best renowned for numerous fossil mammals and birds excavated over the past century. Less researched are insects, even though these specimens frequently serve as the most valuable paleoenvironemental indicators due to their narrow climate restrictions and life cycles. Our goal was to examine fossil material that included insect-plant associations, and thus an even higher potential for significant paleoenviromental data. Micro-CT scans of two exceptionally preserved leafcutter bee nest cells from the Rancho La Brea Tar Pits in Los Angeles, California reveal intact pupae dated between ∼23,000-40,000 radiocarbon years BP. Here identified as best matched to Megachile (Litomegachile gentilis Cresson (Hymenoptera: Megachilidae based on environmental niche models as well as morphometrics, the nest cells (LACMRLP 388E document rare preservation and life-stage. The result of complex plant-insect interactions, they offer new insights into the environment of the Late Pleistocene in southern California. The remarkable preservation of the nest cells suggests they were assembled and nested in the ground where they were excavated. The four different types of dicotyledonous leaves used to construct the cells were likely collected in close proximity to the nest and infer a wooded or riparian habitat with sufficient pollen sources for larval provisions. LACMRLP 388E is the first record of fossil Megachile Latreille cells with pupae. Consequently, it provides a pre-modern age location for a Nearctic group, whose phylogenetic relationships and biogeographic history remain poorly understood. Megachile gentilis appears to respond to climate change as it has expanded its distribution across elevation gradients over time as estimated by habitat suitability comparisons between low and high elevations; it currently inhabits mesic habitats which occurred at a lower

  20. Leafcutter bee nests and pupae from the Rancho La Brea Tar Pits of Southern California: implications for understanding the paleoenvironment of the Late Pleistocene.

    Science.gov (United States)

    Holden, Anna R; Koch, Jonathan B; Griswold, Terry; Erwin, Diane M; Hall, Justin

    2014-01-01

    The Rancho La Brea Tar Pits is the world's richest and most important Late Pleistocene fossil locality and best renowned for numerous fossil mammals and birds excavated over the past century. Less researched are insects, even though these specimens frequently serve as the most valuable paleoenvironemental indicators due to their narrow climate restrictions and life cycles. Our goal was to examine fossil material that included insect-plant associations, and thus an even higher potential for significant paleoenviromental data. Micro-CT scans of two exceptionally preserved leafcutter bee nest cells from the Rancho La Brea Tar Pits in Los Angeles, California reveal intact pupae dated between ∼23,000-40,000 radiocarbon years BP. Here identified as best matched to Megachile (Litomegachile) gentilis Cresson (Hymenoptera: Megachilidae) based on environmental niche models as well as morphometrics, the nest cells (LACMRLP 388E) document rare preservation and life-stage. The result of complex plant-insect interactions, they offer new insights into the environment of the Late Pleistocene in southern California. The remarkable preservation of the nest cells suggests they were assembled and nested in the ground where they were excavated. The four different types of dicotyledonous leaves used to construct the cells were likely collected in close proximity to the nest and infer a wooded or riparian habitat with sufficient pollen sources for larval provisions. LACMRLP 388E is the first record of fossil Megachile Latreille cells with pupae. Consequently, it provides a pre-modern age location for a Nearctic group, whose phylogenetic relationships and biogeographic history remain poorly understood. Megachile gentilis appears to respond to climate change as it has expanded its distribution across elevation gradients over time as estimated by habitat suitability comparisons between low and high elevations; it currently inhabits mesic habitats which occurred at a lower elevation during

  1. IGORR 2: Proceedings of the 2. meeting of the International Group On Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-07-01

    The International group on Research Reactors was formed to facilitate the sharing of knowledge and experience among those institutions and individuals who are actively working to design, build, and promote new research reactors or to make significant upgrades to existing facilities. Sessions during this second meeting were devoted to research reactor reports (GRENOBLE reactor, FRM-II, HIFAR, PIK, reactors at JAERI, MAPLE, ANS, NIST, MURR, TRIGA, BR-2, SIRIUS 2); other neutron sources; and two workshops were dealing with research and development results and needs and reports on progress in needed of R and D areas identified at IGORR 1.

  2. IGORR 2: Proceedings of the 2. meeting of the International Group On Research Reactors

    International Nuclear Information System (INIS)

    1992-01-01

    The International group on Research Reactors was formed to facilitate the sharing of knowledge and experience among those institutions and individuals who are actively working to design, build, and promote new research reactors or to make significant upgrades to existing facilities. Sessions during this second meeting were devoted to research reactor reports (GRENOBLE reactor, FRM-II, HIFAR, PIK, reactors at JAERI, MAPLE, ANS, NIST, MURR, TRIGA, BR-2, SIRIUS 2); other neutron sources; and two workshops were dealing with research and development results and needs and reports on progress in needed of R and D areas identified at IGORR 1

  3. Escarabajos estercoleros (Coleoptera: Scarabaeidae: Scarabaeinae de ranchos ganaderos de Yucatán, México Dung beetles (Coleoptera: Scarabaeidae: Scarabaeinae from cattle ranches of Yucatán, Mexico

    Directory of Open Access Journals (Sweden)

    Gertrudis Basto-Estrella

    2012-06-01

    Full Text Available Este estudio describe la fauna de escarabajos estercoleros (Scarabaeidae: Scarabaeinae en ranchos ganaderos del trópico subhúmedo. De enero a diciembre de 2010 se recolectaron 93 274 escarabajos estercoleros pertenecientes a 17 especies de la subfamilia Scarabaeinae con trampas de caída libre cebadas con excremento de ganado bovino en 4 ranchos ganaderos del oriente del estado de Yucatán, México. Las especies más abundantes fueron Onthophagus landolti, seguida por Canthon indigaceus chevrolati, Digitonthophagus gazella, C. leechi y Pseudocanthon perplexus. Se observó que las especies cavadoras tuvieron mayor abundancia y riqueza; las diurnas de talla pequeña tuvieron menor riqueza pero fueron más abundantes en todo el estudio. El conocimiento de la composición faunística de escarabajos estercoleros de la región es un punto de partida para desarrollar estudios del impacto de las actividades humanas y las prácticas de producción ganadera sobre la diversidad de estos insectos.This study describes the fauna of dung beetles (Scarabaeidae: Scarabaeinae in tropical sub-humid cattle ranches. Insects were collected with pitfall traps baited with cattle manure from January to December 2010 in four cattle ranches of eastern state of Yucatán, Mexico. 93 274 dung beetles were collected from 17 species of the subfamily Scarabaeinae. The most abundant species were Onthophagus landolti, followed by Canthon indigaceus chevrolati, Digitonthophagus gazella, C. leechi y Pseudocanthon perplexus. Observations showed that burrowing species had greater abundance and species richness. Diurnal species of small size had lower richness, but were more abundant. Knowledge of the composition of dung beetle fauna of the region is a starting point to develop studies of the impact of human activities and livestock production practices on the diversity of these insects.

  4. Proposed strategy for improving capulín cultivation in the municipalities of Domingo Arenas, Calpan and San Nicolas de los Ranchos

    Directory of Open Access Journals (Sweden)

    Luz María Páez Reyes

    2013-01-01

    Full Text Available Currently the municipalities of Domingo Arenas, Calpan and San Nicolás de los Ranchos Puebla State, conditions and have a favorable climate for growing capulín, however, not being given adequate management value the crop, This causes the yields are low and its economic importance is unnoticed. The aim of the investigation was "explore how to improve the economic and productive use capulín through the revaluation of the same by the producers, because of the advantages offered by the cultivation in its management and low investment”. For data collection a semistructured interview wasapplied to 15 key informants five municipality respectively. For data analysis tool was used the problem tree and a SWOT. Among the outstanding results we found that capulín has opportunities that can be exploited as an economic alternative for low-income producers or for the unemployed, because their characteristics and management can be easily cultivated.

  5. Commuter exposure to PM2.5, BC, and UFP in six common transport microenvironments in Sacramento, California

    Science.gov (United States)

    Ham, Walter; Vijayan, Abhilash; Schulte, Nico; Herner, Jorn D.

    2017-10-01

    This study was designed to estimate and compare the air pollution exposures experienced by commuters in six common transportation modes utilized by California residents, and to evaluate the impact of practical exposure mitigation strategies in reducing commute exposures. We measured concentrations of fine particle matter (PM2.5), black carbon (BC), and ultrafine particles (UFP) for 161 commutes between April 2014 and November 2015 in Sacramento, CA. We collected measurements for six modes including single occupancy vehicles, high occupancy vehicles (multiple occupants), buses, light rail, train, and bicycling. The largest average concentrations for most pollutants were measured during train commutes and the lowest average concentrations were observed during light-rail commutes. Mitigation options were explored for personal vehicles, bicycling, and train commute modes. We found that ventilation settings of personal vehicles can reduce in-vehicle PM2.5, BC, and UFP concentrations by up to 75%. Similarly, bicycle route choice can reduce exposures by 15-75% with the lowest concentrations observed during commutes on dedicated bicycle paths away from traffic sources. Train commuters experienced UFP concentrations an order of magnitude greater when the locomotive engine was pulling the rail cars versus pushing the rail cars. We found that UFP concentrations during bus, bicycling, and train commutes were 1.6-5.3 times greater than personal vehicle commutes, while light rail commutes had 30% lower UFP concentrations than personal vehicle commutes. The largest exposure per mile occurred during bicycle commutes with PM2.5, BC, and UFP exposures of 1.312 μg/mile, 0.097 μg/mile, and 3.0 × 109 particles/mile, respectively. Train commutes experienced the largest exposure per mile of all of the combustion-derived transportation commute modes. BC accounted for 5-20% of total PM mass across all commute modes with an average fraction of ∼7% of PM2.5.

  6. Characterization of the Three Mile Island Unit-2 reactor building atmosphere prior to the reactor building purge

    International Nuclear Information System (INIS)

    Hartwell, J.K.; Mandler, J.W.; Duce, S.W.; Motes, B.G.

    1981-05-01

    The Three Mile Island Unit-2 reactor building atmosphere was sampled prior to the reactor building purge. Samples of the containment atmosphere were obtained using specialized sampling equipment installed through penetration R-626 at the 358-foot (109-meter) level of the TMI-2 reactor building. The samples were subsequently analyzed for radionuclide concentration and for gaseous molecular components (O 2 , N 2 , etc.) by two independent laboratories at the Idaho National Engineering Laboratory (INEL). The sampling procedures, analysis methods, and results are summarized

  7. Radiation protection at the RA Reactor in 1998, RA reactor annual report, Part -2

    International Nuclear Information System (INIS)

    Ninkovic, M.; Pavlovic, R.; Mandic, M.; Pavlovic, S.; Grsic, Z.

    1998-01-01

    Radiation protection tasks which enable safe operation of the RA reactor, and are defined according the the legal regulations and IAEA safety recommendations are sorted into four categories in this report: (1) Control of the working environment, dosimetry at the RA reactor; (2) Radioactivity control in the vicinity of the reactor and meteorology measurements; (3) Collecting and treatment of fluid effluents; and (4) radioactive wastes, decontamination and actions. Each of the category is described as a separate annex of this report [sr

  8. USO DE PLANTAS EM PÓ SECO COM PROPRIEDADES TERMITICIDA SOBRE A MORTALIDADE DE CUPINS ARBÓREOS

    Directory of Open Access Journals (Sweden)

    Chistopher Stallone Cruz

    2012-09-01

    Full Text Available 1024x768 Normal 0 21 false false false PT-BR X-NONE X-NONE Os térmitas são insetos de grande importância ecológica, com mais de 2.750 espécies catalogadas em todo o mundo. Pequeno número de espécies são conhecidos por provocarem grandes danos econômicos ao homem, sendo considerado como praga urbana ou agrícola, são destruidores de madeira seca, pastagens e outros materiais composto de celulose. A vasta gama de uso indiscriminado de produtos químicos contra o controle deste inseto vem trazendo ao longo do tempo resultados negativos, por apresentarem sérios riscos a saúde humana e dar surgimento a cupins com resistência. Avaliou-se nove espécies vegetais que possivelmente apresentem poder cupinicida em substituição aos tratamentos convencionais, de modo a preservar o meio ambiente. Foram avaliados os seguintes vegetais: caule e folha de Aspidosperma pyrifolium, raiz de Mimosa tenuiflora, raiz de Cnidoscolus urens, gema apical de Syzygium aromaticum, semente de Azadirachta indica, fruto de Piper nigrum, folhas de Eucalyptus sp., raiz de Zingiber officinale e fruto de Punica granatum. Foram coletados 550 espécimes de cupins, 275 operários e 275 soldados, logo em seguida foram distribuídos 10 indivíduos dentro de um cativeiro de polipropileno com capacidade de 250mL, juntamente com 3g do pó seco, 5g de fragmentos de cupinzeiro macerado, verificando a viabilidade dos pós secos durante 5 dias consecutivos, sendo realizado uma leitura de mortalidade a cada 24 horas. O delineamento utilizado foi o inteiramente casualizado e os dados foram avaliados pelos testes Student e Henderson & Tilton. Verificou-se que a utilização dos pós vegetais é  alternativa eficaz e barata no controle de Nasutitermes sp., destacando-se como mais letais folhas e galhos de A. indica,Eucalyptus sp., S. aromaticum, Z. officinale, C. urens e P. nigrum.

  9. Active species in a large volume N2-O2 post-discharge reactor

    International Nuclear Information System (INIS)

    Kutasi, K; Pintassilgo, C D; Loureiro, J; Coelho, P J

    2007-01-01

    A large volume post-discharge reactor placed downstream from a flowing N 2 -O 2 microwave discharge is modelled using a three-dimensional hydrodynamic model. The density distributions of the most populated active species present in the reactor-O( 3 P), O 2 (a 1 Δ g ), O 2 (b 1 Σ g + ), NO(X 2 Π), NO(A 2 Σ + ), NO(B 2 Π), NO 2 (X), O 3 , O 2 (X 3 Σ g - ) and N( 4 S)-are calculated and the main source and loss processes for each species are identified for two discharge conditions: (i) p = 2 Torr, f = 2450 MHz, and (ii) p = 8 Torr, f = 915 MHz; in the case of a N 2 -2%O 2 mixture composition and gas flow rate of 2 x 10 3 sccm. The modification of the species relative densities by changing the oxygen percentage in the initial gas mixture composition, in the 0.2%-5% range, are presented. The possible tuning of the species concentrations in the reactor by changing the size of the connecting afterglow tube between the active discharge and the large post-discharge reactor is investigated as well

  10. G 2 reactor project; Projet de pile a double fin: G 2

    Energy Technology Data Exchange (ETDEWEB)

    Ailleret, [Electricite de France (EDF), Dir. General des Etudes de Recherches, 75 - Paris (France); Taranger, P; Yvon, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    The CEA actually constructs the G-2 reactor core working with natural uranium, which will use graphite as moderator, and gas under pressure as cooling fluid. This report presents the specificity of the new reactor: - the different elements of the reactor core, - the control and the security of the reactor, - the renewal of the fuel, - the biologic surrounding wall, - and the cooling circuit. (M.B.) [French] le Commissariat a l'Energie Atomique construit actuellement la pile G-2 a Uranium naturel, qui utilisera le graphite comme moderateur, et le gaz sous pression comme fluide de refroidissement. Ce rapport presente les specificite du nouveau reacteur: - les differents elements de la pile, - le controle et la securite du reacteur, - le renouvellement du combustible, - l'enceinte biologique, - et le circuit de refroidissement. (M.B.)

  11. Reactor handbook. 2. rev. ed.

    International Nuclear Information System (INIS)

    Lederer, B.J.; Wildberg, D.W.

    1992-01-01

    On the basis of the guidelines on expert knowledge, the book discusses the subjects of atomic physics, heat transfer, nuclear power plants, reactor materials, radiation protection, reactor safety, reactor instrumentation, and reactor operation, with special regard to nuclear power plants with LWR-type reactors. The book is intended for shift personnel, especially gang bosses, reactor operators, and control station operators: for this reason a practical and rather popular style has been chosen. However, the book will also be a manual for other operating personnel, personnel of producer companies, expert organisations, authorities, and students. It can be used as a textbook for staff training, a manual for the practice, and as accompanying book for teaching at nuclear engineering schools. (orig.) With 173 figs [de

  12. Características do sêmen de carneiros Dorper, Santa Inês e sem padrão racial definido, pré e pós-congelação, nos períodos chuvoso e seco

    Directory of Open Access Journals (Sweden)

    J.M. Frazão Sobrinho

    2014-08-01

    Full Text Available Avaliaram-se as características espermáticas de carneiros Dorper, Santa Inês e sem padrão racial definido, nos períodos chuvoso e seco. Após ser colhido por vagina artificial, o sêmen foi avaliado quanto ao volume, ao turbilhonamento, à motilidade, ao vigor, à morfologia e à concentração, congelado e armazenado em botijão criogênico. Depois de descongelado, foram avaliadas a cinemática espermática, a integridade da membrana plasmática, a integridade do acrossoma e a atividade mitocondrial. Vigor espermático, motilidade total, motilidade progressiva, velocidade em linha reta e defeitos maiores não diferiram entre os períodos chuvoso e seco, porém volume, turbilhonamento, linearidade, retilinearidade e frequência de batimentos de cauda foram mais baixos (P<0,05 no período seco; já concentração espermática e defeitos totais apresentaram valores mais baixos no período chuvoso. Valores de integridade do acrossoma e da membrana plasmática, bem como o potencial de membrana mitocondrial, foram mais baixos (P<0,05 no período seco. Conclui-se que os períodos chuvoso e seco influenciam na qualidade espermática de ovinos criados na região Meio-Norte do Brasil e que esses animais têm uma qualidade espermática superior no período chuvoso, quando, portanto, deve ocorrer a criopreservação. Também se observou que, em relação à qualidade espermática, o melhor grupo de carneiros foi o Santa Inês.

  13. Successes, Failures and Suggested Future Directions for Ecosystem Restoration of the Middle Sacramento River, California

    OpenAIRE

    Gregory H. Golet; David L. Brown; Melinda Carlson; Thomas Gardali; Adam Henderson; Karen D. Holl; Christine A. Howell; Marcel Holyoak; John W. Hunt; G. Mathias Kondolf; Eric W. Larsen; Ryan A. Luster; Charles McClain; Charles Nelson; Seth Paine

    2013-01-01

    Large-scale ecosystem restoration projects seldom undergo comprehensive evaluation to determine project effectiveness. Consequently, there are missed opportunities for learning and strategy refinement. Before our study, monitoring information from California’s middle Sacramento River had not been synthesized, despite restoration having been ongoing since 1989. Our assessment was based on the development and application of 36 quantitative ecological indicators. These indicators were used to ch...

  14. Análisis de vulnerabilidad mediante modelamiento hidrodinámico del cauce del río seco del Cono Sur de la ciudad de Tacna

    OpenAIRE

    Frisancho Camero, Felix Ladislao

    2015-01-01

    La cuenca del río Seco tiene un área de 1 106,49 Km2 y una cuenca húmeda de 344,74 Km2, contando con el aporte de tres sub cuencas: Caplina , Palca y Vilavilani Yungane. Se analizó las variables del estudio, siendo la población que habita en la zona, infraestructura urbana y la hidrología y geología de la cuenca. Mediante el análisis de frecuencias se estimaron las precipitaciones, intensidades o caudales máximos, para diferentes períodos de retorno, mediante la aplicación de modelos probabil...

  15. Cuantificacion de huevo en fideos secos según metodo electroforético (SDS PAGUE) Quantification of egg in dried noodles by electrophoretic methods (SDS PAGE)

    OpenAIRE

    LB López; K Cellerino; MJ Binaghi; MS Giacomino; ME Valencia

    2011-01-01

    La cuantificación de huevo en fideos secos elaborados con harina y agregado de huevo. Se analizaron 6 sistemas modelos (SM) de fideos que contenían 0,0; 1,0; 2,5; 4,0; 6,0 y 8,0% de huevo en polvo. Se extrajeron proteínas totales con un buffer que contiene dodecilsulfato de sodio (SDS) y 2-Mercaptoetanol y se realizó electroforesis en gel de poliacrilamida con SDS. Se establecieron las relaciones de las áreas de los picos de los densitogramas (de huevo y de trigo) que permiten una correcta cu...

  16. New horizontal and vertical mass transfer coefficient equation formulations applied to a refinery data base

    International Nuclear Information System (INIS)

    Hellums, L.J.; Fine, D.G.; DeCoursey, S.S.; Cronic, K.A.

    1984-01-01

    The American Petroleum Institute (API) has collected a large tracer data base representing the best field data on atmospheric dispersion performed up to 1982. Twelve of these tracer programs (Hanford 67, Green Glow, Prairie Grass, NRTS, TMI, Ocean Breeze, Dry Gulch, St. Louis, Rancho Seco, Paramount, Karlsruhe, Goodyear) were brought into Phillips Petroleum Company for Gaussian plume formulation using an optimal least squares procedure. The horizontal diffusion and the vertical diffusion were manipulated in an optimal fashion in the Gaussian plume formulation to give a best fit of calculated to experimental (field observations) data important conclusions from the many observations in this work are: 1. Field measured Turner stability when used with Pasquill-Gifford curves does not choose horizontal and vertical dispersion rates representative of true atmospheric turbulence in most cases, 2. Individual stabilities are required rather than assuming one stability for both dispersion rates, and 3. Horizontal diffusion is a function of downwind distance, crosswind distance, and stability for dispersion downwind of building complexes with considerable ground roughness

  17. Annual report on JEN-1 and JEN-2 Reactors; Informe periodico de Reactores JEN-1 y JEN-2 correpondiente al ano 1972

    Energy Technology Data Exchange (ETDEWEB)

    Montes Ponce de Leon, J.

    1974-07-01

    In the annual report on the JEN-1 and JEN-2 reactors the main fractures of the reactor operations and maintenance are described. The reactor has been in operation for 2188 hours, what means 74% of the total working time. Maintenance and periodical tests have occupied the rest of the time. Maintenance operations are shown according to three main subjects, the main failures so as the reactor scrams are also described. Different date relating with radiation level and health Physics are also included. (Author)

  18. Optimized Control Rods of the BR2 Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kalcheva, Silva; Koonen, E.

    2007-09-15

    At the present time the BR-2 reactor uses control elements with cadmium as neutron absorbing part. The lower section of the control element is a beryllium assembly cooled by light water. Due to the burn up of the lower end of the cadmium section during the reactor operation, the presently used rods for reactivity control of the BR-2 reactor have to be replaced by new ones. Considered are various types Control Rods with full active part of the following materials: cadmium (Cd), hafnium (Hf), europium oxide (Eu2O3) and gadolinium (Gd2O3). Options to decrease the burn up of the control rod material in the hot spot, such as use of stainless steel in the lower active part of the Control Rod are discussed. Comparison with the characteristics of the presently used Control Rods types is performed. The changing of the characteristics of different types Control Rods and the perturbation effects on the reactor neutronics during the BR-2 fuel cycle are investigated. The burn up of the Control Rod absorbing material, total and differential control rods worth, macroscopic and effective microscopic absorption cross sections, fuel and reactivity evolution are evaluated during approximately 30 operating cycles.

  19. Optimized Control Rods of the BR2 Reactor

    International Nuclear Information System (INIS)

    Kalcheva, Silva; Koonen, E.

    2007-01-01

    At the present time the BR-2 reactor uses control elements with cadmium as neutron absorbing part. The lower section of the control element is a beryllium assembly cooled by light water. Due to the burn up of the lower end of the cadmium section during the reactor operation, the presently used rods for reactivity control of the BR-2 reactor have to be replaced by new ones. Considered are various types Control Rods with full active part of the following materials: cadmium (Cd), hafnium (Hf), europium oxide (Eu2O3) and gadolinium (Gd2O3). Options to decrease the burn up of the control rod material in the hot spot, such as use of stainless steel in the lower active part of the Control Rod are discussed. Comparison with the characteristics of the presently used Control Rods types is performed. The changing of the characteristics of different types Control Rods and the perturbation effects on the reactor neutronics during the BR-2 fuel cycle are investigated. The burn up of the Control Rod absorbing material, total and differential control rods worth, macroscopic and effective microscopic absorption cross sections, fuel and reactivity evolution are evaluated during approximately 30 operating cycles.

  20. AVALIAÇÃO DE PROPRIEDADES MECÂNICAS DA MADEIRA DE Eucalyptus urograndis SECOS

    Directory of Open Access Journals (Sweden)

    João Marcelo Soares Pereira

    2017-04-01

    Full Text Available O presente trabalho teve como objetivo avaliar as propriedades mecânicas de cisalhamento e compressão de corpos de prova de Eucalyptus urograndis secos. Os seis corpos de prova utilizados no estudo foram retirados de peças de calços com quatorze anos de idade, para cada ensaio mecânico: cisalhamento (fv0, compressão paralela às fibras (fc0 e normal às fibras (fc90. Os valores médios de resistência obtidos nos ensaios de cisalhamento, compressão paralela às fibras e normal às fibras foram 10,30 MPa, 59,17 MPa e 9,20 MPa, respectivamente. Todos os valores obtidos alcançaram valores médios acima da referência estabelecidos pela NBR 7190 (1997.

  1. Inhibidores de la germinación en el residuo seco del tallo del amaranto (Amaranthus hypochondriacus)

    OpenAIRE

    Tejeda-Sartorius, Olga; Escalante-Estrada, J. Alberto; Soto-Hernández, Marcos; Rodríguez-González, Ma. Teresa; Vibrans, Heike; Ramírez-Guzmán, Martha E.

    2004-01-01

    Se evaluó el efecto del extracto acuoso del residuo seco del tallo del amaranto (Amaranthus hypochondriacus L. var. Azteca) a diferentes concentraciones, en la germinación y longitud de radícula y vástago de Amaranthus hybridus L. Dicho extracto, a 108 y 54 ppm inhibió la germinación de la especie en 100% y 68.42%, respectivamente, disminuyendo significativamente la longitud del vástago y la radícula, cuando la inhibición de la germinación no fue total. Se identificaron los ácidos ferúlico (A...

  2. Upgrading of the research reactors FRG-1 and FRG-2

    International Nuclear Information System (INIS)

    Krull, W.

    1981-01-01

    In 1972 for the research reactor FRG-2 we applied for a license to increase the power from 15 MW to 21 MW. During this procedure a public laying out of the safety report and an upgrading procedure for both research reactors - FRG-1 (5 MW) and FRG-2 - were required by the licensing authorities. After discussing the legal background for licensing procedures in the Federal Republic of Germany the upgrading for both research reactors is described. The present status and future licensing aspects for changes of our research reactors are discussed, too. (orig.) [de

  3. Ecología de la dispersión de plantas en los bosques secos del suroccidente Ecuatoriano

    OpenAIRE

    Jara Guerrero, Andrea Katherine

    2014-01-01

    La importancia del proceso de dispersión de semillas en la estructura y dinámica de los ecosistemas es ampliamente reconocida. Sin embargo, para los bosques tropicales estacionalmente secos los estudios relacionados con este proceso son aún escasos y dispersos en comparación con los bosques tropicales lluviosos. En este trabajo se estudió la importancia de los síndromes de dispersión de semillas en la estructuración de comunidades, mediante el análisis de los patrones de dispersión de semilla...

  4. Changes in the status of harvested rice fields in the Sacramento Valley, California: Implications for wintering waterfowl.

    Science.gov (United States)

    Miller, Michael R.; Garr, Jay D.; Coates, Peter S.

    2010-01-01

    Harvested rice fields provide critical foraging habitat for wintering waterfowl in North America, but their value depends upon post-harvest treatments. We visited harvested ricefields in the Sacramento Valley, California, during the winters of 2007 and 2008 (recent period) and recorded their observed status as harvested (standing or mechanically modified stubble), burned, plowed, or flooded. We compared these data with those from identical studies conducted during the 1980s (early period). We documented substantial changes in field status between periods. First, the area of flooded rice increased 4-5-fold, from about 15% to >40% of fields, because of a 3-4-fold increase in the percentage of fields flooded coupled with a 37-41% increase in the area of rice produced. Concurrently, the area of plowed fields increased from 35% of fields, burned fields declined from about 40% to 1%, and fields categorized as harvested declined from 22-54% to rice field status survey in the Sacramento Valley and other North American rice growing regions as appropriate to support long-term monitoring programs and wetland habitat conservation planning for wintering waterfowl.

  5. Effects of the proposed California WaterFix North Delta Diversion on survival of juvenile Chinook salmon (Oncorhynchus tshawytscha) in the Sacramento-San Joaquin River Delta, northern California

    Science.gov (United States)

    Perry, Russell W.; Pope, Adam C.

    2018-05-11

    The California Department of Water Resources and Bureau of Reclamation propose new water intake facilities on the Sacramento River in northern California that would convey some of the water for export to areas south of the Sacramento-San Joaquin River Delta (hereinafter referred to as the Delta) through tunnels rather than through the Delta. The collection of water intakes, tunnels, pumping facilities, associated structures, and proposed operations are collectively referred to as California WaterFix. The water intake facilities, hereinafter referred to as the North Delta Diversion (NDD), are proposed to be located on the Sacramento River downstream of the city of Sacramento and upstream of the first major river junction where Sutter Slough branches from the Sacramento River. The NDD can divert a maximum discharge of 9,000 cubic feet per second (ft3 /s) from the Sacramento River, which reduces the amount of Sacramento River inflow into the Delta. In this report, we conduct four analyses to investigate the effect of the NDD and its proposed operation on survival of juvenile Chinook salmon (Oncorhynchus tshawytscha). All analyses used the results of a Bayesian survival model that allowed us to simulate travel time, migration routing, and survival of juvenile Chinook salmon migrating through the Delta in response to NDD operations, which affected both inflows to the Delta and operation of the Delta Cross Channel (DCC). For the first analysis, we evaluated the effect of the NDD bypass rules on salmon survival. The NDD bypass rules are a set of operational rule curves designed to provide adaptive levels of fish protection by defining allowable diversion rates as a function of (1) Sacramento River discharge as measured at Freeport, and (2) time of year when endangered runs requiring the most protection are present. We determined that all bypass rule curves except constant low-level pumping (maximum diversion of 900 ft3 /s) could cause a sizeable decrease in survival by as

  6. Annual report on JEN-1 and JEN-2 Reactors

    International Nuclear Information System (INIS)

    Montes Ponce de Leon, J.

    1974-01-01

    In the annual report on the JEN-1 and JEN-2 reactors the main fractures of the reactor operations and maintenance are described. The reactor has been in operation for 2188 hours, what means 74% of the total working time. Maintenance and periodical tests have occupied the rest of the time. Maintenance operations are shown according to three main subjects, the main failures so as the reactor scrams are also described. Different date relating with radiation level and health Physics are also included. (Author)

  7. REPTILES DEL VALLE SECO DEL RÍO MAGDALENA (HUILA, COLOMBIA

    Directory of Open Access Journals (Sweden)

    RAFAEL MORENO-ARIAS

    2015-06-01

    Full Text Available Se presenta una caracterización de la fauna de reptiles del valle seco del río Magdalena en el departamento del Huila, así como la comparación faunística entre unidades de cobertura vegetal y épocas climáticas. Se registraron 31 especies pertenecientes a 30 géneros, 17 familias y dos órdenes. En el orden Squamata, la familia más diversa fue Teiidae (lagartijas con tres especies y Colubridae (serpientes con nueve. Para el orden Testudines se registró una especie. Con base en curvas de acumulación de especies y los estimadores no paramétricos Jackknife 2 y Bootstrap, para las lagartijas se obtuvo una alta representatividad en el muestreo (83% y 92% respectivamente, mientras que para las serpientes fue menor (75% y 82% respectivamente. La estructura y composición de los ensambles de reptiles en cada unidad de cobertura vegetal no fue significativamente diferente, en general se caracterizaron por presentar pocas especies con muchos individuos y numerosas especies raras. El arbustal presentó la mayor riqueza de especies seguido del bosque de ribera y los cultivos de cacao. En general la abundancia de reptiles fue mayor en la época de lluvias que en la época seca, sin embargo la manera en que responden las especies a las épocas climáticas está dada por sus características ecológicas, fisiológicas y comportamentales.

  8. Delivering Economic Development in the Context of Financial Crisis: A Workforce Gap Analysis of the Sacramento Regional Economy

    Science.gov (United States)

    Taghavian, Alexander H.

    2013-01-01

    Workforce development represents a central priority in a comprehensive effort to create wealth, industry thickening, and broad-based prosperity. From the onset of the Great Recession in 2007, the Sacramento Region experienced anemic economic growth and remained behind the nation in job creation. Contextualized in the aftermath of the economic…

  9. System Design of a Supercritical CO_2 cooled Micro Modular Reactor

    International Nuclear Information System (INIS)

    Kim, Seong Gu; Cho, Seongkuk; Yu, Hwanyeal; Kim, Yonghee; Jeong, Yong Hoon; Lee, Jeong Ik

    2014-01-01

    Small modular reactor (SMR) systems that have advantages of little initial capital cost and small restriction on construction site are being developed by many research organizations around the world. Existing SMR concepts have the same objective: to achieve compact size and a long life core. Most of small modular reactors have much smaller size than the large nuclear power plant. However, existing SMR concepts are not fully modularized. This paper suggests a complete modular reactor with an innovative concept for reactor cooling by using a supercritical carbon dioxide. The authors propose the supercritical CO_2 Brayton cycle (S-CO_2 cycle) as a power conversion system to achieve small volume of power conversion unit (PCU) and to contain the reactor core and PCU in one vessel. A conceptual design of the proposed small modular reactor was developed, which is named as KAIST Micro Modular Reactor (MMR). The supercritical CO_2 Brayton cycle for the S-CO_2 cooled reactor core was optimized and the size of turbomachinery and heat exchanger were estimated preliminary. The nuclear fuel composed with UN was proposed and the core lifetime was obtained from a burnup versus reactivity calculation. Furthermore, a system layout with fully passive safety systems for both normal operation and emergency operation was proposed. (author)

  10. Low-Level Waste Forum notes and summary reports for 1994. Volume 9, Number 3, May-June 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    This issue includes the following articles: Vermont ratifies Texas compact; Pennsylvania study on rates of decay for classes of low-level radioactive waste; South Carolina legislature adjourns without extending access to Barnwell for out-of-region generators; Southeast Compact Commission authorizes payments for facility development, also votes on petitions, access contracts; storage of low-level radioactive waste at Rancho Seco removed from consideration; plutonium estimates for Ward Valley, California; judgment issued in Ward Valley lawsuits; Central Midwest Commission questions court`s jurisdiction over surcharge rebates litigation; Supreme Court decides commerce clause case involving solid waste; parties voluntarily dismiss Envirocare case; appellate court affirms dismissal of suit against Central Commission; LLW Forum mixed waste working group meets; US EPA Office of Radiation and Indoor Air rulemakings; EPA issues draft radiation site cleanup regulation; EPA extends mixed waste enforcement moratorium; and NRC denies petition to amend low-level radioactive waste classification regulations.

  11. Low-Level Waste Forum notes and summary reports for 1994. Volume 9, Number 3, May-June 1994

    International Nuclear Information System (INIS)

    1994-06-01

    This issue includes the following articles: Vermont ratifies Texas compact; Pennsylvania study on rates of decay for classes of low-level radioactive waste; South Carolina legislature adjourns without extending access to Barnwell for out-of-region generators; Southeast Compact Commission authorizes payments for facility development, also votes on petitions, access contracts; storage of low-level radioactive waste at Rancho Seco removed from consideration; plutonium estimates for Ward Valley, California; judgment issued in Ward Valley lawsuits; Central Midwest Commission questions court's jurisdiction over surcharge rebates litigation; Supreme Court decides commerce clause case involving solid waste; parties voluntarily dismiss Envirocare case; appellate court affirms dismissal of suit against Central Commission; LLW Forum mixed waste working group meets; US EPA Office of Radiation and Indoor Air rulemakings; EPA issues draft radiation site cleanup regulation; EPA extends mixed waste enforcement moratorium; and NRC denies petition to amend low-level radioactive waste classification regulations

  12. The SLOWPOKE-2 reactor with low enrichment uranium oxide fuel

    International Nuclear Information System (INIS)

    Townes, B.M.; Hilborn, J.W.

    1985-06-01

    A SLOWPOKE-2 reactor core contains less than 1 kg of highly enriched uranium (HEU) and the proliferation risk is very low. However, to overcome proliferation concerns a new low enrichment uranium (LEU) fuelled reactor core has been designed. This core contains approximately 180 fuel elements based on the Zircaloy-4 clad UOsub(2) CANDU fuel element, but with a smaller outside diameter. The physics characteristics of this new reactor core ensure the inherent safety of the reactor under all conceivable conditions and thus the basic SLOWPOKE safety philosophy which permits unattended operation is not affected

  13. Análisis y diseño de un esquema de control para aplicación en baño seco portátil

    Directory of Open Access Journals (Sweden)

    Leobardo Hernández González

    2014-01-01

    Full Text Available Actualmente, la industria aplica rigurosos estándares de calidad en sus procesos de producción, obligándose a contar con instrumentos de medición cada vez más exactos. Lo que exige que para obtener una certificación, en muchos casos se tenga que calibrar sus instrumentos fuera de las propias instalaciones, generando diversas dificultades debido a la imposibilidad de parar los procesos de producción. En algunos casos, se contrata a empresas especializadas para realizar la calibración dentro de la planta, pero generalmente resulta una operación parcial, costosa e incómoda. Como una solución práctica se propone un baño de bloque seco portátil basado en las Celdas Peltier, que permita la calibración de sensores de temperatura, con las características de fácil transportación y manejo, para realizar dicha calibración en la propia planta de producción. El prototipo experimental de baño de bloque seco permite alcanzar un rango de temperatura que va de los 0°C hasta los 150°C (273,2°k a 423,2°k, recurrente en muchos procesos industriales. Para asegurar un correcto control de temperatura se propone un algoritmo de control digital PID, implantado en un micro controlador tipo PiC. El sistema de control de temperatura se validó con simulaciones y pruebas experimentales para todo el sistema en funcionamiento, obteniéndose resultados bastantes satisfactorios.

  14. Operation of the SLOWPOKE-2 reactor in Jamaica

    Energy Technology Data Exchange (ETDEWEB)

    Grant, C.N.; Lalor, G.C.; Vuchkov, M.K. [University of the West Indies, Kingston (Jamaica)

    2001-07-01

    Over the past sixteen years lCENS has operated a SLOWPOKE 2 nuclear reactor almost exclusively for the purpose of neutron activation analysis. During this period we have adopted a strategy of minimum irradiation times while optimizing our output in an effort to increase the lifetime of the reactor core and to maintaining fuel integrity. An inter-comparison study with results obtained with a much larger reactor at IPEN has validated this approach. The parameters routinely monitored at ICENS are also discussed and the method used to predict the next shim adjustment. (author)

  15. Irradiation techniques at BR2 reactor

    International Nuclear Information System (INIS)

    Hebel, W.

    1978-01-01

    Since 1963 the material testing reactor BR2 at Mol is operated for the realisation of numerous research programs and experiments on the behavior of materials under nuclear radiation and in particular under intensive neutron exposure. During this period special irradiation techniques and experimental devices were developed according to the desiderata of the different experiments and to the irradiation possibilities offered at BR2. The design and the operating characteristics of quite a number of those irradiation rigs of proven reliability may be used or can be made available for new irradiation experiments. A brief description is given of some typical irradiation devices designed and constructed by CEN/SCK, Technology and Energy Dpt. They are compiled according to their main use for the different research and development programs realized at BR2. Their eventual application however for different objectives could be possible. A final chapter summarizes the principal irradiation conditions offered by BR2 reactor. (author)

  16. El uso de granos secos de destilería con solubles (DDGS) en dietas sorgo-soya para pollos de engorda y gallinas de postura

    OpenAIRE

    Arturo Cortes Cuevas; César A. Esparza Carrillo; Gonzalo Sanabria Elizalde; Jorge Miguel Iriarte; Manuel Ornelas Roac; Ernesto Ávila González

    2012-01-01

    Para estudiar el comportamiento productivo en pollos y gallinas con dietas adicionadass con granos secos de destilería con solubles (DDGS), se realizaron dos experimentos. En el primero se emplearon 704 pollos Ross de 1 a 49 días de edad, distribuidos en cuatro tratamientos con ocho repeticiones de 22 pollos cada uno. Se empleó un diseño completamente al azar. Los tratamientos fueron: 1) dieta basal sorgo-soya, T2) como 1+7% DDGS, T3) como 1+14% de DDGS, T4) como 1+21% de DDGS. En el segundo ...

  17. Popular Music: A Selected Bibliography of Materials in the California State University, Sacramento Library. Bibliographic Series No. 22.

    Science.gov (United States)

    Smith, Donna Ridley, Comp.

    The bibliography lists over 400 works in the California State University Library, Sacramento, on pop, rock, country, folk, blues, and soul music from 1950 to the present. Books, periodicals, and non-book materials noted in the bibliography are appropriate for history, communication studies, and popular culture studies as well as for music. Items…

  18. Conflicts in River Management: A Conservationist's Perspective on Sacramento River Riparian Habitats—Impacts, Threats, Remedies, Opportunities, and Consensus

    Science.gov (United States)

    Richard Spotts

    1989-01-01

    The Sacramento River's historic riparian habitats have been reduced by over 98 percent due to cumulative, adverse human activities. These activities continue to jeopardize the remaining riparian habitats. The results of these trends is more endangered species conflicts and listings, coupled with less fish, beautiful scenery, and other resource values. This paper...

  19. Different impacts of hypertension and diabetes mellitus on all-cause and cardiovascular mortality in community-dwelling older adults: the Rancho Bernardo Study.

    Science.gov (United States)

    Oh, Jee-Young; Allison, Matthew A; Barrett-Connor, Elizabeth

    2017-01-01

    Although the prevalence rates of hypertension (HTN) and diabetes mellitus are slowing in some high-income countries, HTN and diabetes mellitus remain as the two major risk factors for atherosclerotic cardiovascular disease (CVD), the leading cause of death in the United States and worldwide. We aimed to observe the association of HTN and diabetes mellitus with all-cause and CVD mortality in older white adults. All community-dwelling Rancho Bernardo Study participants who were at least 55 years old and had carefully measured blood pressure and plasma glucose from 75-g oral glucose tolerance test at the baseline visit (1984-1987, n = 2186) were followed up until death or the last clinic visit in 2013 (median 14.3 years, interquartile range 8.4-21.3). In unadjusted analyses, diabetes mellitus was associated with all-cause mortality [hazard ratio 1.40, 95% confidence interval (CI) 1.23-1.60] and CVD mortality (hazard ratio 1.67, 95% CI 1.39-2.00); HTN with all-cause mortality [hazard ratio 1.93 (1.73-2.15)] and CVD mortality [hazard ratio 2.45 (2.10-2.93)]. After adjustment for cardiovascular risk factors, including age, BMI, triglycerides, HDL-cholesterol, smoking, exercise, and alcohol consumption, diabetes mellitus was associated with CVD mortality only (hazard ratio 1.25, P = 0.0213). Conversely, HTN was associated with both all-cause (hazard ratio 1.34, P diabetes mellitus and HTN was associated with all-cause (hazard ratio 1.38, P = 0.0002) and CVD mortality (hazard ratio 1.70, P diabetes mellitus. Having both confers a modest increase in the hazards for these types of mortality.

  20. Maíz, potencial productivo y seguridad alimentaria: el caso de San Nicolás de Los Ranchos, Puebla-México

    Directory of Open Access Journals (Sweden)

    Miguel A. Damián Huato

    2016-01-01

    Full Text Available Se expone un modelo tecnológico para aumentar el potencial productivo de maíz de secano, validado con productores de San Nicolás de los Ranchos Puebla-México. Se calculó el Índice de Apropiación de Tecnologías Radicales (IATR y el Grado de Empleo de Tecnologías Progresivas (GETP; se agruparon a los productores según su rendimiento para diseñar el modelo tecnológico y se estimó la seguridad alimentaria real y potencial. Se encontró que: en el manejo de maíz interaccionan innovaciones radicales y progresivas imperando las segundas; no hay relación directa entre el IATR y rendimientos, pero sí con el GETP; que 29% de los productores son eficientes; el 29% de los productores no poseen seguridad alimentaria y que si los productores de bajo y medio potencial productivo, aplicaran el patrón tecnológico de los productores eficientes, los rendimientos aumentarían, en promedio un 157% y 38%, respectivamente.

  1. Bats (Mammalia: Chiroptera in native and reforested areas in Rancho Alegre, Paraná, Brazil

    Directory of Open Access Journals (Sweden)

    Patrícia Helena Gallo

    2010-12-01

    Full Text Available Generally, natural environments have been transformed into small forest remnants, with the consequent habitat loss and species extinction. The North Paraná State is not an exception, since only 2 to 4% of the original ecosystem occurs in small fragments of Stational Semidecidual Forest. We studied the species richness and abundance of bats in two forest fragments from the Fazenda Congonhas, in Rancho Alegre city, Paraná State, Brazil. Four samplings were undertaken in a legally protected native area (107.8ha and in a reforested area (11.8ha between April 2007 and March 2008. Samplings began at nightfall and lasted six hours, during two consecutive nights in each location. The individuals were captured using eight mist nets, with the same capture effort in both environments. A total of 397 individuals, 14 species and 10 genera were captured in the native area; while in the reforested area, 105 individuals, six species and four genera. Artibeus lituratus was the most common species in both fragments (n=328, 65.3%, followed by Artibeus fimbriatus (n=44, 8.8% and Artibeus jamaicensis (n=30, 6.0%. Other species including Platyrrhinus lineatus, Carollia perspicillata, Sturnira lilium, Chrotopterus auritus, Desmodus rotundus, Michronycteris megalotis, Phyllostomus hastatus, Phyllostomus discolor, Myoti levis, Myotis nigricans and Lasiurus blossevillii, accounted for 19.9% of the captures. The native area presented higher values of species richness (S=14 and diversity (H’=1.4802 in comparison to the reforested area (S=6, H’=0.57015. The t-test evidenced a significant difference between diversity among the sites (t=7.1075. Chao 1 index indicated that the sampling effort recorded approximately 78% from the total species richness for the native area and 75% for the reforested area. Therefore, the preservation of the forest fragment is essential since it provides habitat for a diverse community of bats. Forest management and reforestation actions may

  2. TMI-2 reactor vessel head removal

    International Nuclear Information System (INIS)

    Bengel, P.R.; Smith, M.D.; Estabrook, G.A.

    1985-09-01

    This report describes the safe removal and storage of the Three Mile Island Unit 2 (TMI-2) reactor vessel head. The head was removed in July 1984 to permit the removal of the plenum and the reactor core, which were damaged during the 1979 accident. From July 1982, plans and preparations were made using a standard head removal procedure modified by the necessary precautions and changes to account for conditions caused by the accident. After data acquisition, equipment and structure modifications, and training, the head was safely removed and stored; and the internals indexing fixture and a work platform were installed on top of the vessel. Dose rates during and after the operation were lower than expected; lessons were learned from the operation which will be applied to the continuing fuel removal operations activities

  3. TMI-2 reactor vessel plenum final lift

    International Nuclear Information System (INIS)

    Wilson, D.C.

    1986-01-01

    Removal of the plenum assembly from the TMI-2 reactor vessel was necessary to gain access to the core region for defueling. The plenum was lifted from the reactor vessel by the polar crane using three specially designed pendant assemblies. It was then transferred in air to the flooded deep end of the refueling canal and lowered onto a storage stand where it will remain throughout the defueling effort. The lift and transfer were successfully accomplished on May 15, 1985 in just under three hours by a lift team located in a shielded area within the reactor building. The success of the program is attributed to extensive mockup and training activities plus thorough preparations to address potential problems. 54 refs

  4. Erratum dated 2014 June 25: Fate and Transport of Three Pharmaceuticals in the Sacramento-San Joaquin Delta

    Directory of Open Access Journals (Sweden)

    Minta M. Schaefer

    2013-06-01

    Full Text Available Pharmaceuticals and personal care products (PPCPs are found in surface waters worldwide. Wastewater treatment plant effluent is a major source of these contaminants. The Sacramento–San Joaquin Delta (Delta is a unique aquatic ecosystem, a source of drinking water for over 25 million Californians, and a primary source of water for Central Valley agriculture. The sharp decline of four pelagic fish species in the Delta in the last decade is just one of several indicators that the ecosystem is severely impaired. Several wastewater treatment plants (WWTPs discharge into the Delta, directly or through tributaries. The presence of PPCPs in the Delta has received very little attention relative to the immense effort underway to rehabilitate the ecosystem. This study determined concentrations of PPCPs in the Sacramento River in the vicinity of the Sacramento Regional Wastewater Treatment Plant using passive sampler monitoring. These data were used to estimate loads of three of the detected pharmaceuticals (carbamazepine, fluoxetine, and trimethoprim from nine other WWTPs that discharge to the Delta. The 2-D, finite element, Resource Management Associates (RMA Delta Model was then applied to determine the distribution that might result from these discharges. The model was run for the 2006, 2007, and 2009 water years. Results indicate that it is feasible that WWTP discharges could result in chronic presence of these pharmaceuticals at low ng L-1 levels at all 45 model output locations and, therefore, aquatic organisms within the Delta may be continually exposed to these contaminants.

  5. NOAA TIFF Image - 1m Multibeam Bathymetry, US Virgin Islands - Vieques Island (El Seco) - Project NF-09-01 - (2009), UTM 20N NAD83 (NCEI Accession 0131857)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This dataset contains a unified ESRI Grid with 1x1 meter cell size representing the bathymetry of El Seco, a selected portion of seafloor east of Vieques Island,...

  6. NOAA TIFF Image - .75m Multibeam Backscatter, US Virgin Islands - Vieques Island (El Seco) - Project NF-09-01 - (2009), UTM 20N WGS 84 (NCEI Accession 0131857)

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — This dataset contains a GeoTIFF with .75x.75 meter cell size representing the backscatter or intensity of sound returned from the seafloor in "El Seco" east of...

  7. Refurbishment programme for the BR2-reactor

    Energy Technology Data Exchange (ETDEWEB)

    Koonen, E [Centre d' Etude de l' Energie Nucleaire, Studiecentrum voor Kernenergie, BR2 Department, Boeretang, Mol (Belgium)

    1992-07-01

    BR2 is a high flux engineering test reactor, which differs from comparable material testing reactors by its specific core array (fig. 1). It is a heterogeneous, thermal, tank-in-pool type reactor, moderated by beryllium and light water, which serves also as coolant. The fuel elements consist of cylindrical assemblies loaded in channels materialized by hexagonal beryllium prisms. The central 200 mm channel is vertical, while all others are inclined and form a hyperbolical arrangement around the central one. This feature combines a very compact core with the requirement of sufficient space for individual access to all channels through penetrations in the top cover of the aluminium pressure vessel. Each channel may hold a fuel element, a control rod, an experiment, an irradiation device or a beryllium plug. The refurbishment Program According to the present programme of C.E.N./S.C.K., BR2 will be in operation until 1996. At that time, the beryllium matrix will reach its foreseen end-of-life. In order to continue operation beyond this point, a thorough refurbishment of the reactor is foreseen, in addition to the unavoidable replacement of the matrix, to ensure quality of the installation and compliance with modern standards. Some fundamental options have been taken as a starting point: BR2 will continue to be used as a classical MTR, i.e. fuel and material irradiations and safety experiments with some additional service-activities. The present configuration is optimized for that use and there is no specific experimental requirement to change the basic concepts and performance characteristics. From the customers viewpoint, it is desirable to go ahead with the well-known features of BR2, to maintain a high degree of availability and reliability and to minimize the duration of the long shutdown. It is also important to limit the amount of nuclear liabilities. So the objective of the refurbishment programme is the life extension of BR2 for about 15 years, corresponding to

  8. Refurbishment programme for the BR2-reactor

    International Nuclear Information System (INIS)

    Koonen, E.

    1992-01-01

    BR2 is a high flux engineering test reactor, which differs from comparable material testing reactors by its specific core array (fig. 1). It is a heterogeneous, thermal, tank-in-pool type reactor, moderated by beryllium and light water, which serves also as coolant. The fuel elements consist of cylindrical assemblies loaded in channels materialized by hexagonal beryllium prisms. The central 200 mm channel is vertical, while all others are inclined and form a hyperbolical arrangement around the central one. This feature combines a very compact core with the requirement of sufficient space for individual access to all channels through penetrations in the top cover of the aluminium pressure vessel. Each channel may hold a fuel element, a control rod, an experiment, an irradiation device or a beryllium plug. The refurbishment Program According to the present programme of C.E.N./S.C.K., BR2 will be in operation until 1996. At that time, the beryllium matrix will reach its foreseen end-of-life. In order to continue operation beyond this point, a thorough refurbishment of the reactor is foreseen, in addition to the unavoidable replacement of the matrix, to ensure quality of the installation and compliance with modern standards. Some fundamental options have been taken as a starting point: BR2 will continue to be used as a classical MTR, i.e. fuel and material irradiations and safety experiments with some additional service-activities. The present configuration is optimized for that use and there is no specific experimental requirement to change the basic concepts and performance characteristics. From the customers viewpoint, it is desirable to go ahead with the well-known features of BR2, to maintain a high degree of availability and reliability and to minimize the duration of the long shutdown. It is also important to limit the amount of nuclear liabilities. So the objective of the refurbishment programme is the life extension of BR2 for about 15 years, corresponding to

  9. Losses of Sacramento River Chinook Salmon and Delta Smelt to Entrainment in Water Diversions in the Sacramento–San Joaquin Delta

    Directory of Open Access Journals (Sweden)

    Wim J. Kimmerer

    2008-06-01

    Full Text Available Pumping at the water export facilities in the southern Sacramento-San Joaquin Delta kills fish at and near the associated fish-salvage facilities. Correlative analyses of salvage counts with population indices have failed to provide quantitative estimates of the magnitude of this mortality. I estimated the proportional losses of Sacramento River Chinook salmon (Oncorhynchus tshawytscha and delta smelt (Hypomesus transpacificus to place these losses in a population context. The estimate for salmon was based on recoveries of tagged smolts released in the upper Sacramento River basin, and recovered at the fish-salvage facilities in the south Delta and in a trawling program in the western Delta. The proportion of fish salvaged increased with export flow, with a mean value around 10% at the highest export flows recorded. Mortality was around 10% if pre-salvage losses were about 80%, but this value is nearly unconstrained. Losses of adult delta smelt in winter and young delta smelt in spring were estimated from salvage data (adults corrected for estimated pre-salvage survival, or from trawl data in the southern Delta (young. These losses were divided by population size and accumulated over the respective seasons. Losses of adult delta smelt were 1–50% (median 15% although the highest value may have been biased upward. Daily losses of larvae and juveniles were 0–8%, and seasonal losses accumulated were 0–25% (median 13%. The effect of these losses on population abundance was obscured by subsequent 50-fold variability in survival from summer to fall.

  10. Población y ocupación del espacio en la frontera del salado. Chascomús, Ranchos y Monte entre 1815 y 1838

    Directory of Open Access Journals (Sweden)

    Guillermo Banzato

    2000-06-01

    Full Text Available Los numerosos estudios sobre la sociedad rural rioplatense en el período colonial y pos independiente van mostrando, poco a poco, las características de la población, la composición familiar y la disponibilidad de mano de obra, tanto en las áreas de viejo asentamiento como en las más dinámicas de la frontera interior, de manera que puede continuarse la tarea con nuevas aproximaciones, comparando los resultados con los ya obtenidos. Esta será la perspectiva del presente trabajo, en el que se describirá la estructura poblacional de Chascomús entre 1815 y 1838, aunque sumando una relación que se aprecia ausente en los trabajos sobre el tema, como es la ocupación y acceso a la propiedad legal de la tierra. Debido a las características de las fuentes los partidos de Ranchos y Monte se incluirán parcialmente en el análisis

  11. Reação entre a performance em natação e variáveis de força em seco. Um estudo piloto em nadadoras de nível nacional.

    OpenAIRE

    Amaro, Nuno

    2012-01-01

    Este trabalho apresenta uma revisão em torno das questões das manifestações de força em seco e sua relação com a performance de nado. Adicionalmente, foi realizado um estudo piloto para avaliação de procedimentos e metodologias a utilizar em situação de avaliação e controlo de treino. Da revisão da literatura é possível verificar que poucos são os estudos existentes que demonstrem a importância de um programa de treino em seco como complementar ao treino em água. São detetadas ...

  12. A relação entre performance em natação e variáveis de força em seco : um estudo piloto em nadadoras de nível nacional

    OpenAIRE

    Amaro, Nuno Miguel Pires Alves

    2012-01-01

    Este trabalho apresenta uma revisão em torno das questões das manifestações de força em seco e sua relação com a performance de nado. Adicionalmente, foi realizado um estudo piloto para avaliação de procedimentos e metodologias a utilizar em situação de avaliação e controlo de treino. Da revisão da literatura é possível verificar que poucos são os estudos existentes que demonstrem a importância de um programa de treino em seco como complementar ao treino em água. São detetadas ...

  13. Audit Report on the Sacramento Army Depot Internal Review and Audit Compliance Office's "Audits of Warranties, Quality Deficiency Reports, and Reports of Discrepancies"

    National Research Council Canada - National Science Library

    1992-01-01

    The Sacramento Army Depot (SAAD) Internal Review and Audit Compliance Office (Internal Review) issued an audit report, "Audit of Warranties, Quality Deficiency Reports, and Reports of Discrepancies," on July 20, 1990...

  14. Refurbishing the BR2 materials testing reactor

    International Nuclear Information System (INIS)

    Baugnet, J.M.; Dekeyser, J.; Gubel, P.

    1995-01-01

    SCK/CEN is refurbishing its BR2 reactor to allow its further operation during the next 15 years; in doing so, it chooses to keep BR2 available for future scientific and technological irradiation programs within an international context. (author) 2 figs

  15. Evaluación de agentes de coagulación para la producción de láminas de caucho seco a partir de Látex multiclonal de “Hevea Brasiliensis”

    OpenAIRE

    Giraldo Díaz, Alejandra María; López Aristizábal, Paulina

    2016-01-01

    El presente trabajo consiste en la evaluación de tres agentes de coagulación, uno convencional (ácido acético) y dos alternativos (ácido cítrico y limoneno) para la producción de láminas de caucho seco a partir del látex de Hevea brasiliensis, extraído del Nordeste Antioqueño en el corregimiento San José del Nus -- Se realizó una caracterización del látex, en la que se obtuvo una densidad de 0,97 gr/ml, un porcentaje de solidos de 31,14%, un porcentaje de caucho seco de 29,4%, un TGA con la p...

  16. Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966

    International Nuclear Information System (INIS)

    1966-01-01

    This Volume 2 of the Proceedings of 2. Yugoslav symposium on reactor physics includes eight papers dealing with the following topics: method for measuring high anti reactivities of a reactor system; integration method for thermal reaction rate calculation; Determination of initial core configuration for BHWR-200 MWe; safety shutdowns and failures of the RA reactor equipment; determining the reactivity of absorption rods; measurements of thermal and fast neutron fluxes at the TRIGA reactor and other measurements during operation of the TRIGA reactor; mathematical modelling of the reactor safety; review of problems and methods for radiation risk assessment in the environment of a nuclear power plant

  17. SIRIUS 2: A versatile medium power research reactor

    International Nuclear Information System (INIS)

    Rousselle, P.

    1992-01-01

    Most of the Research Reactors in the world have been critical in the Sixties and operated for twenty to thirty years. Some of them have been completely shut down, modified, or simply refurbished; the total number of RR in operation has decreased but there is still an important need for medium power research reactors in order: - to sustain a power program with fuel and material testing for NPP or fusion reactors; - to produce radioisotopes for industrial or medical purposes, doped silicon, NAA or neutron radiography; - to investigate further the condensed matter, with cold neutrons routed through neutron guides to improved equipment; - to develop new technologies and applications such as medical alphatherapy. Hence, taking advantage of nearly hundred reactor x years operation and backed up by the CEA experience, TECHNICATOME assisted by FRAMATOME has designed a new versatile multipurpose Research Reactor (20-30 Mw) SIRIUS 2 taking into account: - more stringent safety rules; - the lifetime; - the flexibility enabling a wide range of experiments and, - the future dismantling of the facility according to the ALARA criteria

  18. Reparación de un dique seco en el Ferrol/España

    Directory of Open Access Journals (Sweden)

    Navas Gutiérrez, Mariano

    1981-06-01

    Full Text Available El dique seco de El Ferrol, construido como dique de gravedad según la técnica de la época (1913, ha sufrido una serie de averías como consecuencia de su envejecimiento, que ha obligado a emprender una obra de reparación según las modernas técnicas de soleras ancladas y drenadas, y pantallas de bentonita-cemento. Se ha construido una losa de 30 cm en el antedique, anclada con armaduras activas, formado cada anclaje por diez cables según una malla de 3 x 3 m. Para aliviar la subpresión se ha colocado un dren entre la solera permeable actualmente existente y la losa. Con la pantalla de bentonita-cemento se pretende cerrar la entrada de agua por el relleno permeable del antiguo dique. El terreno natural es prácticamente impermeable.

  19. Efeito do salbutamol liberado através de inalador de pó seco sobre o broncoespasmo induzido por metacolina Effects of salbutamol delivered by dry-powder inhaler on methacholine-induced bronchoconstriction

    Directory of Open Access Journals (Sweden)

    Adalberto Sperb Rubin

    2004-06-01

    Full Text Available INTRODUÇÃO: Os beta2-agonistas de curta duração sob a forma de nebulímetro pressurizado são os fármacos utilizados rotineiramente na reversão do broncoespasmo induzido pela metacolina. A administração desses fármacos na forma de pó seco, liberados por inaladores de pó seco pode ser uma alternativa eficaz. OBJETIVO: Avaliar a efetividade e rapidez de ação do salbutamol liberado através de inalador de pó seco pulvinal (Butovent® na reversão do broncoespasmo induzido por metacolina, comparando-o com o salbutamol liberado por nebulímetro pressurizado. MÉTODO: Foram avaliados prospectivamente 60 pacientes sucessivos com broncoespasmo induzido por metacolina, cuja queda do volume expiratório forçado no primeiro segundo (VEF1 foi de, no mínimo, 20%. Foram randomizados 30 pacientes para receber 200 mcg de salbutamol liberado por nebulímetro pressurizado e 30 pacientes para receber 200 mcg de salbutamol através de inalador de pó seco (pulvinal, na etapa final do teste de broncoprovocação, com o objetivo de reverter o broncoespasmo induzido pela metacolina. Foram avaliados os VEF1 obtidos 1 minuto e 5 minutos após a administração do broncodilatador. RESULTADOS: Os grupos foram pareados por sexo, idade, peso, altura, dose provocativa causadora de queda de 20% no VEF1 (primeiro grupo: 1,3 mg ; segundo grupo: 1,19 mg; p = 0,79 e VEF1 pós-metacolina (primeiro grupo: 2,03 l; segundo grupo: 1,99 l; p = 0,87, sem diferença significativa entre eles. O incremento médio do VEF1 foi de 16,2% (1 minuto e 22,2% (5 minutos no primeiro grupo e de 17% (1 minuto e 23,6% (5 minutos no segundo grupo, não havendo diferença estatística entre eles (p = 0,8. CONCLUSÕES: Os beta2-agonistas administrados através de inalador de pó seco (pulvinal apresentam a mesma eficácia broncodilatadora e rapidez de ação que no tradicional método por nebulímetro pressurizado.BACKGROUND: Short-acting beta2 agonists delivered by metered-dose inhaler

  20. OTUS - Reactor inventory management system based on ORIGEN2

    Energy Technology Data Exchange (ETDEWEB)

    Poellaenen, R; Toivonen, H; Lahtinen, J; Ilander, T

    1995-10-01

    ORIGEN2 is a computer code that calculates nuclide composition and other characteristics of nuclear fuel. The use of ORIGEN2 requires good knowledge in reactor physics. However, once the input has been defined for a particular reactor type, the calculations can be easily repeated for any burnup and decay time. This procedure produces large output files that are difficult to handle manually. A new computer code, known as OTUS, was designed to facilitate the postprocessing of the data. OTUS makes use of the inventory files precalculated with ORIGEN2 in a way that enables their versatile treatment for different safety analysis purposes. A data base is created containing a comprehensive set of ORIGEN2 calculations as a function of fuel burnup and decay time. OTUS is a reactor inventory management system for a microcomputer with Windows interface. Four major data operations are available: (1) Build data modifies ORIGEN2 output data into a suitable format, (2) View data enables flexible presentation of the data as such, (3) Different calculations, such as nuclide ratios and hot particle characteristics, can be performed for severe accident analyses, consequence analyses and research purposes, (4) Summary files contain both burnup dependent and decay time dependent inventory information related to the nuclide and the reactor specified. These files can be used for safeguards, radiation monitoring and safety assessment. (orig.) (22 refs., 29 figs.).

  1. Advanced Power Electronics Interfaces for Distributed Energy Workshop Summary: August 24, 2006, Sacramento, California

    Energy Technology Data Exchange (ETDEWEB)

    Treanton, B.; Palomo, J.; Kroposki, B.; Thomas, H.

    2006-10-01

    The Advanced Power Electronics Interfaces for Distributed Energy Workshop, sponsored by the California Energy Commission Public Interest Energy Research program and organized by the National Renewable Energy Laboratory, was held Aug. 24, 2006, in Sacramento, Calif. The workshop provided a forum for industry stakeholders to share their knowledge and experience about technologies, manufacturing approaches, markets, and issues in power electronics for a range of distributed energy resources. It focused on the development of advanced power electronic interfaces for distributed energy applications and included discussions of modular power electronics, component manufacturing, and power electronic applications.

  2. The 2nd reactor core of the NS Otto Hahn

    International Nuclear Information System (INIS)

    Manthey, H.J.; Kracht, H.

    1979-01-01

    Details of the design of the 2nd reactor core are given, followed by a brief report summarising the operating experience gained with this 2nd core, as well as by an evaluation of measured data and statements concerning the usefulness of the knowledge gained for the development of future reactor cores. Quite a number of these data have been used to improve the concept and thus the specifications for the fuel elements of the 3rd core of the reactor of the NS Otto Hahn. (orig./HP) [de

  3. Data of evolutionary structure change: 2A3TA-2PPDB [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 2A3TA-2PPDB 2A3T 2PPD A B --------LPRVKHTLVPPPFAHAHEQVAASGPVINEFE...YEDTVKVMRTLTPTHVVFNGAVGALTGDKAMTAAVGEKVLIVHSQANRDTRPHLIGGHGDYVWATGKFNTPPDVDQETWFI...ne> GLN CA 428 2PPD B 2PPD...ax> 1 2PPD... B 2PPDB CAPPG-MVPWA <seco

  4. Enfriamiento de café pergamino seco a granel utilizando aireación mecánica controlada

    Directory of Open Access Journals (Sweden)

    Julio E. Ospina M.

    1992-05-01

    Full Text Available Con el fin de garantizar que el café almacenado a granel conserve su calidad durante el tiempo necesario de almacenamiento, se estudió el enfriamiento del café pergamino seco en silos experimentales de dimensiones: 0.5m x 0.5m y 2.8 m de altura, utilizando aire enfriado mecánicamente. Los rangos estudiados fueron: temperatura de 10 a 220C humedad relativa de 66 a 98%y contenido de humedad del grano de 8 a 13.57% b.h. Durante la etapa de almacenamiento se evaluó la variación de la calidad del café según los criterios de coloración de la almendra, población de microorganismos y prueba de taza; paralelamente se dejaron muestras almacenadas en sacosa las condiciones de Chinchiná, como muestra testigo buscando determinar la bondad del almacenamiento a granel, también se dejó un silo sin aireación para determinar el efecto de la aireación controlada en la calidad del café.

  5. EL-2 reactor: Thermal neutron flux distribution

    International Nuclear Information System (INIS)

    Rousseau, A.; Genthon, J.P.

    1958-01-01

    The flux distribution of thermal neutrons in EL-2 reactor is studied. The reactor core and lattices are described as well as the experimental reactor facilities, in particular, the experimental channels and special facilities. The measurement shows that the thermal neutron flux increases in the central channel when enriched uranium is used in place of natural uranium. However the thermal neutron flux is not perturbed in the other reactor channels by the fuel modification. The macroscopic flux distribution is measured according the radial positioning of fuel rods. The longitudinal neutron flux distribution in a fuel rod is also measured and shows no difference between enriched and natural uranium fuel rods. In addition, measurements of the flux distribution have been effectuated for rods containing other material as steel or aluminium. The neutron flux distribution is also studied in all the experimental channels as well as in the thermal column. The determination of the distribution of the thermal neutron flux in all experimental facilities, the thermal column and the fuel channels has been made with a heavy water level of 1825 mm and is given for an operating power of 1000 kW. (M.P.)

  6. Physics design of advanced steady-state tokamak reactor A-SSTR2

    International Nuclear Information System (INIS)

    Nishio, Satoshi; Ushigusa, Kenkichi

    2000-10-01

    Based on design studies on the fusion power reactor such as the DEMO reactor SSTR, the compact power reactor A-SSTR and the DREAM reactor with a high environmental safety and high availability, a new concept of compact and economic fusion power reactor (A-SSTR2) with high safety and high availability is proposed. Employing high temperature superconductor, the toroidal filed coils supplies the maximum field of 23T on conductor which corresponds to 11T at the magnetic axis. A-SSTR2 (R p =6.2m, a p =1.5m, I p =12MA) has a fusion power of 4GW with β N =4. For an easy maintenance and for an enough support against a strong electromagnetic force on coils, a poloidal coils system has no center solenoid coils and consists of 6 coils located on top and bottom of the machine. Physics studies on the plasma equilibrium, controllability of the configuration, the plasma initiation and non-inductive current ramp-up, fusion power controllability and the diverter have shown the validity of the A-SSTR2 concept. (author)

  7. FORE-2, Thermohydraulics and Space-Independent Reactor Kinetics for Transients

    International Nuclear Information System (INIS)

    Fox, J.N.; Lawler, B.E.; Butz, H.R.; Heames, T.J.

    1984-01-01

    1 - Description of problem or function: FORE2 is a coupled thermal hydraulics-point kinetics digital computer code designed to calculate significant reactor parameters under steady-state conditions, or as functions of time during transients. The transients may result from a programmed reactivity insertion or a power change. Variable inlet coolant flow rate and temperature are considered. The code calculates the reactor power, the individual reactivity feedbacks, and the temperature of coolant, cladding, fuel, structure, and additional material for up to seven axial positions in three channel types which represent radial zones of the reactor. The heat of fusion, accompanying fuel melting, the liquid metal voiding reactivity, and the spatial and the time variation of the fuel cladding gap coefficient due to changes in gap size are considered. 2 - Method of solution: FORE2 input consists of property data, geometry, power and flow distribution factors, external time varying functions, experimental coefficients, and termination data. The differential equations for fluid flow, heat transfer, and point neutronics are solved by explicit finite-difference procedures. 3 - Restrictions on the complexity of the problem: Reactor excursions which can be calculated are restricted to those transients in which the reactor is not substantially destroyed. As a general rule, changes in reactor geometry and composition during an excursion are limited to those cases in which the reactivity effects of the changes may be considered as small perturbations of the initial system. Thus, accidents involving large-scale disassembly and bulk meltdown of a core are not covered by FORE2. FORE2 is valid only while the core retains its initial geometry

  8. Protozoários ruminais de novilhos de corte criados em pastagem tropical durante o período seco

    OpenAIRE

    Silva,Kellerson Luiz da; Duarte,Eduardo Robson; Freitas,Claudio Eduardo Silva; Abrão,Flávia Oliveira; Geraseev,Luciana Castro

    2014-01-01

    Protozoários do rúmen podem representar 40% do nitrogênio total e 60% do produto final da fermentação e apresentam atividade celulolítica. Neste estudo, objetivou-se quantificar e identificar as populações de protozoários no rúmen de novilhos, criados exclusivamente em pastagem, durante o período seco do ano, no Norte de Minas Gerais. Amostras do suco ruminal de 36 novilhos mestiços Nelore foram coletadas diretamente do rúmen, após o abate, durante o inicio, meio ou fim do período de estiagem...

  9. Keeping research reactors relevant: A pro-active approach for SLOWPOKE-2

    International Nuclear Information System (INIS)

    Cosby, L.R.; Bennett, L.G.I.; Nielsen, K.; Weir, R.

    2010-01-01

    The SLOWPOKE is a small, inherently safe, pool-type research reactor that was engineered and marketed by Atomic Energy of Canada Limited (AECL) in the 1970s and 80s. The original reactor, SLOWPOKE-1, was moved from Chalk River to the University of Toronto in 1970 and was operated until upgraded to the SLOWPOKE-2 reactor in 1973. In all, eight reactors in the two versions were produced and five are still in operation today, three having been decommissioned. All of the remaining reactors are designated as SLOWPOKE-2 reactors. These research reactors are prone to two major issues: aging components and lack of relevance to a younger audience. In order to combat these problems, one SLOWPOKE -2 facility has embraced a strategy that involves modernizing their reactor in order to keep the reactor up to date and relevant. In 2001, this facility replaced its aging analogue reactor control system with a digital control system. The system was successfully commissioned and has provided a renewed platform for student learning and research. The digital control system provides a better interface and allows flexibility in data storage and retrieval that was never possible with the analogue control system. This facility has started work on another upgrade to the digital control and instrumentation system that will be installed in 2010. The upgrade includes new computer hardware, updated software and a web-based simulation and training system that will allow licensed operators, students and researchers to use an online simulation tool for training, education and research. The tool consists of: 1) A dynamic simulation for reactor kinetics (e.g., core flux, power, core temperatures, etc). This tool is useful for operator training and student education; 2) Dynamic mapping of the reactor and pool container gamma and neutron fluxes as well as the vertical neutron beam tube flux. This research planning tool is used for various researchers who wish to do irradiations (e.g., neutron

  10. Calculations of reactor-accident consequences, Version 2. CRAC2: computer code user's guide

    International Nuclear Information System (INIS)

    Ritchie, L.T.; Johnson, J.D.; Blond, R.M.

    1983-02-01

    The CRAC2 computer code is a revision of the Calculation of Reactor Accident Consequences computer code, CRAC, developed for the Reactor Safety Study. The CRAC2 computer code incorporates significant modeling improvements in the areas of weather sequence sampling and emergency response, and refinements to the plume rise, atmospheric dispersion, and wet deposition models. New output capabilities have also been added. This guide is to facilitate the informed and intelligent use of CRAC2. It includes descriptions of the input data, the output results, the file structures, control information, and five sample problems

  11. Thermal reactor benchmark tests on JENDL-2

    International Nuclear Information System (INIS)

    Takano, Hideki; Tsuchihashi, Keichiro; Yamane, Tsuyoshi; Akino, Fujiyoshi; Ishiguro, Yukio; Ido, Masaru.

    1983-11-01

    A group constant library for the thermal reactor standard nuclear design code system SRAC was produced by using the evaluated nuclear data JENDL-2. Furthermore, the group constants for 235 U were calculated also from ENDF/B-V. Thermal reactor benchmark calculations were performed using the produced group constant library. The selected benchmark cores are two water-moderated lattices (TRX-1 and 2), two heavy water-moderated cores (DCA and ETA-1), two graphite-moderated cores (SHE-8 and 13) and eight critical experiments for critical safety. The effective multiplication factors and lattice cell parameters were calculated and compared with the experimental values. The results are summarized as follows. (1) Effective multiplication factors: The results by JENDL-2 are considerably improved in comparison with ones by ENDF/B-IV. The best agreement is obtained by using JENDL-2 and ENDF/B-V (only 235 U) data. (2) Lattice cell parameters: For the rho 28 (the ratio of epithermal to thermal 238 U captures) and C* (the ratio of 238 U captures to 235 U fissions), the values calculated by JENDL-2 are in good agreement with the experimental values. The rho 28 (the ratio of 238 U to 235 U fissions) are overestimated as found also for the fast reactor benchmarks. The rho 02 (the ratio of epithermal to thermal 232 Th captures) calculated by JENDL-2 or ENDF/B-IV are considerably underestimated. The functions of the SRAC system have been continued to be extended according to the needs of its users. A brief description will be given, in Appendix B, to the extended parts of the SRAC system together with the input specification. (author)

  12. Relocation of the 146th Tactical Airlift Wing of the California Air National Guard. Volume 2. Appendices

    Science.gov (United States)

    1985-08-01

    194 / Ruies and Regulations 2721 I reclaimed and reused for agricultuue. Buried utility lines that do not prevent the Nation’s farmland where proposed...of Indians raided the asistencia (Bancroft 1886-1890 Vol. IV). The San Gabriel Mission’s asistencia was part of the Agua Caliente Rancho, granted to...Antonio Lugo and his sons in 1842 (Bancroft 1886-1890 Vol. IV). The Harlem Springs area was included in the Agua Caliente Rancho, so named because of

  13. Wildlife Response to Riparian Restoration on the Sacramento River

    Directory of Open Access Journals (Sweden)

    Gregory H Golet

    2008-06-01

    Full Text Available Studies that assess the success of riparian restoration projects seldom focus on wildlife. More generally, vegetation characteristics are studied, with the assumption that animal populations will recover once adequate habitats are established. On the Sacramento River, millions of dollars have been spent on habitat restoration, yet few studies of wildlife response have been published. Here we present the major findings of a suite of studies that assessed responses of four taxonomic groups (insects, birds, bats, and rodents. Study designs fell primarily into two broad categories: comparisons of restoration sites of different ages, and comparisons of restoration sites with agricultural and remnant riparian sites. Older restoration sites showed increased abundances of many species of landbirds and bats relative to younger sites, and the same trend was observed for the Valley elderberry longhorn beetle (Desmocerus californicus dimorphus, a federally threatened species. Species richness of landbirds and ground-dwelling beetles appeared to increase as restoration sites matured. Young restoration sites provided benefits to species that utilize early successional riparian habitats, and after about 10 years, the sites appeared to provide many of the complex structural habitat elements that are characteristic of remnant forest patches. Eleven-year old sites were occupied by both cavity-nesting birds and special-status crevice-roosting bats. Restored sites also supported a wide diversity of bee species, and had richness similar to remnant sites. Remnant sites had species compositions of beetles and rodents more similar to older sites than to younger sites. Because study durations were short for all but landbirds, results should be viewed as preliminary. Nonetheless, in aggregate, they provide convincing evidence that restoration along the Sacramento River has been successful in restoring riparian habitats for a broad suite of faunal species. Not only did

  14. WWER-1000 reactor simulator. Material for training courses and workshops. 2. ed

    International Nuclear Information System (INIS)

    2005-01-01

    The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series No.12, Reactor Simulator Development (2001). Course material for workshops using a pressurized water reactor (PWR) simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada is presented in the IAEA publication, Training Course Series No. 22, 2nd edition, Pressurized Water Reactor Simulator (2005) and Training Course Series No.23, 2nd edition, Boiling Water Reactor Simulator (2005). This report consists of course material for workshops using the WWER-1000 Reactor Department Simulator from the Moscow Engineering and Physics Institute, Russian Federation

  15. ASAMPSA2 best-practices guidelines for L2 PSA development and applications. Volume 3 - Extension to Gen IV reactors

    International Nuclear Information System (INIS)

    Bassi, C.; Bonneville, H.; Brinkman, H.; Burgazzi, L.; Polidoro, F.; Vincon, L.; Jouve, S.

    2010-01-01

    The main objective assigned to the Work Package 4 (WP4) of the 'ASAMPSA2' project (EC 7. FPRD) consist in the verification of the potential compliance of L2PSA guidelines based on PWR/BWR reactors (which are specific tasks of WP2 and WP3) with Generation IV representative concepts. Therefore, in order to exhibit potential discrepancies between LWRs and new reactor types, the following work was based on the up-to-date designs of: - The European Fast Reactor (EFR) which will be considered as prototypical of a pool-type Sodium-cooled Fast Reactor (SFR); - The ELSY design for the Lead-cooled Fast Reactor (LFR) technology; - The ANTARES project which could be representative of a Very-High Temperature Reactor (VHTR); - The CEA 2400 MWth Gas-cooled Fast Reactor (GFR). (authors)

  16. Una breve descripción de la vegetación, con especial énfasis en las pioneras intermedias de los bosques secos de la Jagua, en la cuenca alta del Rio Magdalena en el Huila

    Directory of Open Access Journals (Sweden)

    William Gerardo Vargas

    2015-01-01

    Full Text Available Se revisó la información existente sobre la flora de los bosques secos del sur del departamento del Huila, con especial interés en la de La Jagua y sus alrededores con el fin de identificar especies pioneras intermedias que puedan apoyar procesos de restauración ecológica y conservación de la biodiversidad. Para los bosques secos del departamento se identificaron 203 especies pioneras intermedias distribuidas en 123 géneros y 45 familias botánicas, mientras que para La Jagua 153 especies agrupadas en 109 géneros y 42 familias, entre las que sobresalen Fabaceae,  Rubiaceae, Malvaceae, Moraceae y Anacardiaceae. Se proponen 85 especies consideradas claves para procesos de conservación, la restauración de los ecosistemas secos de la región dirigida a la generación de hábitat y de conectividad, la producción de recursos para la fauna, así como la producción de leña y madera para las comunidades dentro de un modelo de herramientas de manejo del paisaje.

  17. Current status of restoration work for obstacle and upper core structure in reactor vessel of experimental fast reactor 'Joyo'. 2-2

    International Nuclear Information System (INIS)

    Okuda, Eiji; Ito, Hiromichi; Yoshihara, Shizuya

    2014-01-01

    An accident occurred in experimental fast reactor 'Joyo' in 2007 which is obstruction of fuel change equipment caused by contacting rotating plug and MARICO-2. In addition, we confirmed two happenings in the reactor vessel that (1) Deformation of MARICO-2 subassembly on the in vessel storage rack together with a transfer pot, (2) Deformation of the Upper core structure of 'Joyo' caused by contacting MARICO-2 subassembly and the UCS. We do the restoration work for restoring it. This time, we describe current status of Replacement work of the UCS. (author)

  18. Sterilization of E. coli bacterium in a flowing N2-O2 post-discharge reactor

    International Nuclear Information System (INIS)

    Villeger, S; Cousty, S; Ricard, A; Sixou, M

    2003-01-01

    Effective destruction of Escherichia coli (E. coli) bacteria has been obtained in a flowing N 2 -O 2 microwave post-discharge reactor. The sterilizing agents are the O atoms and the UV emissions of NOβ which are produced by N and O atoms recombination in the reactor. In the following plasma conditions: pressure 5 Torr, flow rate 1 L n min -1 , microwave power of 100 W in a quartz tube of 5 mm, an O atom density of 2.5x10 15 cm -3 is measured by NO titration in the post-discharge reactor with UV emission in a N 2 -(5%)O 2 gas mixture. Full destruction of 10 13 cfu ml -1 E. coli is observed after a treatment time of 25 min. (rapid communication)

  19. Proceedings IEEE Visualization Conference and IEEE Information Visualization Conference (VIS'07 and INFOVIS'07, Sacramento CA, USA, October 28-November 1, 2007)

    NARCIS (Netherlands)

    Chen, M.; Hansen, C.; North, C.; Pang, A.; Wijk, van J.J.

    2007-01-01

    These are the proceedings of the IEEE Visualization Conference 2007 (Vis 2007) and the IEEE Information Visualization Conference 2007 (InfoVis 2007) held during October 28 to November 1, 2007 in Sacramento, California. The power of using computing technology to create useful, effective imagery for

  20. Identifying sources of dissolved organic carbon in agriculturally dominated rivers using radiocarbon age dating: Sacramento-San Joaquin River Basin, California

    Science.gov (United States)

    Sickman, James O.; DiGiorgio, Carol L.; Davisson, M. Lee; Lucero, Delores M.; Bergamaschi, Brian A.

    2010-01-01

    We used radiocarbon measurements of dissolved organic carbon (DOC) to resolve sources of riverine carbon within agriculturally dominated landscapes in California. During 2003 and 2004, average Δ14C for DOC was −254‰ in agricultural drains in the Sacramento–San Joaquin Delta, −218‰ in the San Joaquin River, −175‰ in the California State Water Project and −152‰ in the Sacramento River. The age of bulk DOC transiting the rivers of California’s Central Valley is the oldest reported for large rivers and suggests wide-spread loss of soil organic matter caused by agriculture and urbanization. Using DAX 8 adsorbent, we isolated and measured 14C concentrations in hydrophobic acid fractions (HPOA); river samples showed evidence of bomb-pulse carbon with average Δ14C of 91 and 76‰ for the San Joaquin and Sacramento Rivers, respectively, with older HPOA, −204‰, observed in agricultural drains. An operationally defined non-HPOA fraction of DOC was observed in the San Joaquin River with seasonally computed Δ14C values of between −275 and −687‰; the source of this aged material was hypothesized to be physically protected organic-matter in high clay-content soils and agrochemicals (i.e., radiocarbon-dead material) applied to farmlands. Mixing models suggest that the Sacramento River contributes about 50% of the DOC load in the California State Water Project, and agricultural drains contribute approximately one-third of the load. In contrast to studies showing stabilization of soil carbon pools within one or two decades following land conversion, sustained loss of soil organic matter, occurring many decades after the initial agricultural-land conversion, was observed in California’s Central Valley.

  1. Did saber-tooth kittens grow up musclebound? A study of postnatal limb bone allometry in felids from the Pleistocene of Rancho La Brea.

    Science.gov (United States)

    Long, Katherine; Prothero, Donald; Madan, Meena; Syverson, Valerie J P

    2017-01-01

    Previous studies have demonstrated that the Pleistocene saber-toothed cat Smilodon fatalis had many forelimb adaptations for increased strength, presumably to grapple with and subdue prey. The Rancho La Brea tar pits yield large samples of juvenile limb bones forming a growth series that allow us to examine how Smilodon kittens grew up. Almost all available juvenile limb bones were measured, and reduced major axis fits were calculated to determine the allometric growth trends. Contrary to expectations based on their robust limbs, Smilodon kittens show the typical pattern of growth found in other large felids (such as the Ice Age lion, Panthera atrox, as well as living tigers, cougars, servals, and wildcats) where the limb grows longer and more slender faster than they grow thick. This adaptation is thought to give felids greater running speed. Smilodon kittens do not grow increasingly more robust with age. Instead, they start out robust and follow the ancestral felid growth pattern, while maintaining their robustness compared to other felids. Apparently, the growth of felid forelimbs is highly canalized and their ontogeny is tightly constrained.

  2. Safe dismantling of the SVAFO research reactors R2 and R2-0 in Sweden

    International Nuclear Information System (INIS)

    ARNOLD, Hans-Uwe; BROY, Yvonne; Dirk Schneider

    2017-01-01

    The R2 and R2-0 reactors were part of the Swedish government's research program on nuclear power from the early 1960's. Both reactors were shut down in 2005 following a decision by former operator Studsvik Nuclear AB. The decommissioning of the R2 and R2-0 reactors is divided into three phases. The first phase - awarded to AREVA - involved dismantling of the reactors and associated systems in the reactor pool, treatment of the disassembled components as well as draining, cleaning and emptying the pool. In the second phase, the pool structure itself will be dismantled, while removal of remaining reactor systems, treatment and disposal of materials and clean-up will be carried out in the third stage. The entire work is planned to be completed before the end of this decade. The paper describes the several steps of phase 1 - starting with the team building, followed by the dismantling operations and covers challenges encountered and lessons learned as well. The reactors consist of 5.400 kg aluminum, 6.000 kg stainless steel restraint structures as well as, connection elements of the mostly flanged components (1.000 kg). The most demanding - from a radiological point of view - was the R2-0 reactor that was limited to ∼ 1 m"3 construction volumes but with an extremely heterogeneous activation profile. Based on the calculated radiological entrance data and later sampling, nuclide vectors for both reactors depending on the real placement of the single component and on the material (aluminum and stainless steel) were created. Finally, for the highest activated component from R2 reactor, 85 Sv/h were measured. The dismantling principles - adopted on a safety point of view - were the following: The always protected base area of the ponds served as a flexible buffer area for waste components and packaging. Specific protections were also installed on the walls to protect them from mechanical stress which may occur during dismantling work. A specific work platform was

  3. An urban-forest control measure for ozone in the Sacramento, CA federal non-attainment area (SFNA) Sustainable Cities and Society

    Science.gov (United States)

    Haider Taha; James Wilkinson; Robert Bornstein; Qingfu Xiao; E. Gregory McPherson; Jim Simpson; Charles Anderson; Steven Lau; Janice Lam; Cindy Blain

    2015-01-01

    Urban forest strategies of gradually replacing high emitters of biogenic volatile organic compounds (BVOC) with low-emitting species are being considered as voluntary or emerging control measures for maintenance of the 8-h ozone standard in the Sacramento Federal Non-Attainment Area (SFNA). We describe a regulatory modeling study demonstrating the air-quality impacts...

  4. Benchmark calculations for VENUS-2 MOX -fueled reactor dosimetry

    International Nuclear Information System (INIS)

    Kim, Jong Kung; Kim, Hong Chul; Shin, Chang Ho; Han, Chi Young; Na, Byung Chan

    2004-01-01

    As a part of a Nuclear Energy Agency (NEA) Project, it was pursued the benchmark for dosimetry calculation of the VENUS-2 MOX-fueled reactor. In this benchmark, the goal is to test the current state-of-the-art computational methods of calculating neutron flux to reactor components against the measured data of the VENUS-2 MOX-fuelled critical experiments. The measured data to be used for this benchmark are the equivalent fission fluxes which are the reaction rates divided by the U 235 fission spectrum averaged cross-section of the corresponding dosimeter. The present benchmark is, therefore, defined to calculate reaction rates and corresponding equivalent fission fluxes measured on the core-mid plane at specific positions outside the core of the VENUS-2 MOX-fuelled reactor. This is a follow-up exercise to the previously completed UO 2 -fuelled VENUS-1 two-dimensional and VENUS-3 three-dimensional exercises. The use of MOX fuel in LWRs presents different neutron characteristics and this is the main interest of the current benchmark compared to the previous ones

  5. PCU arrangement of a supercritical CO{sub 2} cooled micro modular reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Seong Gu; Baik, Seungjoon; Cho, Seong Kuk; Oh, Bong Seong; Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of)

    2016-05-15

    As part of the SMR(Small Modular Reactor)s development effort, the authors propose a concept of supercritical CO{sub 2} (S-CO{sub 2}) cooled fast reactor combined with the S-CO{sub 2} Brayton cycle. The reactor concept is named as KAIST Micro Modular Reactor (MMR). The S-CO{sub 2} Brayton cycle has many strong points when it is used for SMR's power conversion unit. It occupies small footprints due to the compact cycle components and simple layout. Thus, a concept of one module containing the S-CO{sub 2} cooled fast reactor and power conversion system is possible. This module can be shipped via ground transportation (by trailer) or marine transportation. In this study, the authors propose a new conceptual layout for the S-CO{sub 2} cooled direct cycle while considering various issues for arranging cycle components. The new design has an improved cycle efficiency (from 31% to 34%) than the earlier version of MMR by reducing pressure drops in the heat exchangers. As a more efficient option, a recompression recuperated cycle was also designed. It improves 5% of thermal efficiency while 18tons of mass can be added in comparison to the simple recuperated cycle. Even if we adopt recompression cycle as a PCU, the weight of module (152tons) is less than the ground transportable limit (260tons)

  6. TMI-2 reactor vessel head removal

    International Nuclear Information System (INIS)

    Bengel, P.R.; Smith, M.D.; Estabrook, G.A.

    1984-12-01

    This report describes the safe removal and storage of the Three Mile Island Unit 2 reactor vessel head. The head was removed in July 1984 to permit the removal of the plenum and the reactor core, which were damaged during the 1979 accident. From July 1982, plans and preparations were made using a standard head removal procedure modified by the necessary precautions and changes to account for conditions caused by the accident. After data acquisition, equipment and structure modifications, and training the head was safely removed and stored and the internals indexing fixture and a work platform were installed on top of the vessel. Dose rates during and after the operation were lower than expected; lessons were learned from the operation which will be applied to the continuing fuel removal operations activities

  7. Múltiples líneas de evidencias aplicadas al estudio de un individuo prehispánico. Sitio Rancho José (Buenos Aires / Multiple lines of evidence applied to the study of a prehispanic individual. Rancho Jose site, Buenos Aires province

    Directory of Open Access Journals (Sweden)

    Florencia Rizzo

    2016-03-01

    Full Text Available En este trabajo presentamos la información osteológica, cronológica, isotópica y de ADN antiguo (ADNa obtenida a partir del análisis de los restos óseos humanos fragmentados correspondientes a un individuo prehispánico recuperado en el sitio Rancho José. Dicho sitio está ubicado en la margen derecha del río Baradero, donde la acción del agua expuso y removió diferentes tipos de materiales arqueológicos. De acuerdo con la excavación realizada en seis perfiles ubicados en el borde de la barranca, se pudo determinar que los hallazgos fueron depositados en un evento de ocupación. En el perfil 5 se recuperaron los restos óseos de un individuo datado 1900±20 años AP, representado solo por la porción superior del esqueleto. En primer lugar, se consideraron los agentes tafonómicos que podrían haber actuado modificando las condiciones de hallazgo y los materiales asociados. Se realizó la determinación del sexo y la estimación de la edad del individuo y se examinaron las diferentes patologías óseas y dentales. Esta información se complementó con datos obtenidos a partir del análisis de ADN mitocondrial (ADNmt antiguo, de isótopos estables (13C, 15N y el relevamiento de micro-restos vegetales en el tártaro dental. Si bien se trata de un individuo altamente fragmentado, conserva su aparato masticatorio completo y su estudio resulta de interés para comparar con otros individuos, tanto de sitios coetáneos como de tiempos posthispánicos. Con ese fin, también se presentan datos isotópicos de dos individuos del sitio posthispánico Cementerio Indígena. Palabras clave: bajíos septentrionales; bioarqueología; tafonomía; ADN mitocondrial; isótopos estables We present osteological, chronological, isotopic, and ancient DNA (aDNA information obtained from the analysis of the fragmented human remains of a prehispanic individual recovered at Rancho José site. The site is situated on the right bank of the Baradero River, where

  8. Energy Savings Calculations for Heat Island Reduction Strategies in Baton Rouge, Sacramento and Salt Lake City

    Energy Technology Data Exchange (ETDEWEB)

    Konopacki, S.; Akbari, H.

    2000-03-01

    In 1997, the US Environmental Protection Agency (EPA) established the ''Heat Island Reduction Initiative'', to quantify the potential benefits of Heat Island Reduction (HIR) strategies (i.e., shade trees, reflective roofs, reflective pavements and urban vegetation) to reduce cooling energy use in buildings, lower the ambient air temperature and improve urban air quality in cities, and reduce CO2 emissions from power plants. Under this initiative, the Urban Heat Island Pilot Project (UHIPP) was created with the objective to investigate the potential of HIR strategies in residential and commercial buildings in three initial UHIPP cities: Baton Rouge, Sacramento and Salt Lake City. This paper summarizes our efforts to calculate the annual energy savings, peak power avoidance and annual C02 reduction of HIR strategies in the three initial cities. In this analysis, we focused on three building types that offer most savings potential: single-family residence, office and retail store. Each building type was characterized in detail by old or new construction and with a gas furnace or an electric heat pump. We defined prototypical building characteristics for each building type and simulated the impact of HIR strategies on building cooling and heating energy use and peak power demand using the DOE-2.IE model. Our simulations included the impact of (1) strategically-placed shade trees near buildings [direct effect], (2) use of high-albedo roofing material on building [direct effect], (3) combined strategies I and 2 [direct effect], (4) urban reforestation with high-albedo pavements and building surfaces [indirect effect] and (5) combined strategies 1, 2 and 4 [direct and indirect effects]. We then estimated the total roof area of air-conditioned buildings in each city using readily obtainable data to calculate the metropolitan-wide impact of HIR strategies. The results show, that in Baton Rouge, potential annual energy savings of $15M could be realized by

  9. Neutronic study using oxide and nitride fuels for the Super Phenix 2 reactor

    International Nuclear Information System (INIS)

    Batista, J.L.; Renke, C.A.C.

    1991-11-01

    This report presents a neutronic analysis and a description of the Super Phenix 2 reactor, taken as reference. We present the methodology and results for cell and global reactor calculations for oxide (U O 2 - Pu O 2 ) and nitride (U N - Pu N) fuels. To conclude we compare the performance of oxide and nitride fuels for the reference reactor. (author)

  10. Shadow corrosion evaluation in the Studsvik R2 reactor

    International Nuclear Information System (INIS)

    Sanders, Ch.; Lysell, G.

    2000-01-01

    Post-irradiation examination has shown that increased corrosion occurs when zirconium alloys are in contact with or in proximity to other metallic objects. The observations indicate an influence of irradiation from the adjacent component as the enhanced corrosion occurs as a 'shadow' of the metallic object on the zirconium surface. This phenomenon could ultimately limit the lifetime of certain zirconium alloy components in the reactor. The Studsvik R2 materials test reactor has an In-Core Autoclave (INCA) test facility especially designed for water chemistry and materials research. The INCA facility has been evaluated and found suitable for shadow corrosion studies. The R2 reactor core containing the INCA facility was modeled with the Monte Carlo N-Particle (MCNP) code in order to evaluate the electron deposition in various materials and to develop a hypothesis of the shadow corrosion mechanism. (authors)

  11. Influência da temperatura de secagem e da concentração de Aerosil®200 nas características dos extratos secos por aspersão da Schinus terebinthifolius Raddi (Anacardiaceae

    Directory of Open Access Journals (Sweden)

    E.A.F. Vasconcelos

    Full Text Available A Schinus terebinthifolius Raddi é muito usada na medicina popular e atualmente como fitomedicamento pelas propriedades antimicrobiana, cicatrizante e antiinflamatória. O objetivo deste trabalho foi avaliar a influência da temperatura de entrada e a concentração de Aerosil®200 nas características de extratos secos por aspersão da Schinus terebinthifolius Raddi. Os extratos preparados com etanol 70 °GL foram secos em Mini-spray dryer, Buchi B191, com adição do adjuvante tecnológico numa proporção de 20:80; 25:75 e 30:70 (p/p Aerosil®200: resíduo seco, variando a temperatura de entrada de 120 °C a 160 °C. A umidade residual, o rendimento final do produto e o aumento da massa frente à umidade relativa controlada de 90 % foram usados como critério de avaliação. A análise de superfície de resposta revelou que à medida que a temperatura e a concentração de Aerosil aumentam, diminui a umidade residual dos extratos, bem como sua higroscopicidade. As melhores condições de secagem foram a temperatura de entrada de 140 °C e 30 % do adjuvante, resultando em rendimento acima de 80 %.

  12. Benchmark tests of JENDL-3.2 for thermal and fast reactors

    International Nuclear Information System (INIS)

    Takano, Hideki

    1995-01-01

    Benchmark calculations for a variety of thermal and fast reactors have been performed by using the newly evaluated JENDL-3 Version-2 (JENDL-3.2) file. In the thermal reactor calculations for the uranium and plutonium fueled cores of TRX and TCA, the k eff and lattice parameters were well predicted. The fast reactor calculations for ZPPR-9 and FCA assemblies showed that the k eff , reactivity worth of Doppler, sodium void and control rod, and reaction rate distribution were in a very good agreement with the experiments. (author)

  13. Radionuclide distribution in TMI-2 reactor building basement liquids and solids

    International Nuclear Information System (INIS)

    Horan, J.T.; McIsaac, C.V.; Keefer, D.G.

    1984-01-01

    As a result of the TMI-2 accident, approximately 2.46 x 10 6 L of contaminated water were released to the Reactor Building basement. The principal fission product release pathway from the damaged core was through the reactor coolant system (RCS) to the pressurizer, through the pressure-operated relief valve (PORV) on the pressurizer to the Reactor Coolant Drain Tank (RCDT), and then through the RCDT rupture disk to the Reactor Building basement. Since August 1979, a number of efforts have been made to determine the location, quantity, and composition of fission products released to the Reactor Building basement. These efforts have included sampling of the basement water and solids, the basement sump pump recirculation line, the RCDT, and visual surveys using a closed circuit television (CCTV) system. The analysis of basement samples has provided data on the physical and radioisotopic characteristics of the liquids and solids. This paper describes the sample collection techniques and discusses radiochemical analyses results

  14. An experimental investigation of fission product release in SLOWPOKE-2 reactors

    International Nuclear Information System (INIS)

    Harnden, A.M.C.

    1995-09-01

    Increasing radiation fields due to a release of fission products in the reactor container of several SLOWPOKE-2 reactors fuelled with a highly-enriched uranium (HEU) alloy core have been observed. It is believed that these increases are associated with the fuel fabrication where a small amount of uranium-bearing material is exposed to the coolant at the end-welds of the fuel element. To investigate this phenomenon samples of reactor water and gas from the headspace above the water have been obtained and examined by gamma spectrometry methods for reactors of various burnups at the University of Toronto, Ecole Polytechnique and Kanata Isotope Production Facility. An underwater visual examination of the fuel core at Ecole Polytechnique has also provided information on the condition of the core. This report (Volume 1) summarizes the equipment, analysis techniques and results of tests conducted at the various reactor sites. The data report is published as Volume 2. (author). 30 refs., 9 tabs., 20 figs

  15. The Oak Ridge Research Reactor: safety analysis: Volume 2, supplement 2

    International Nuclear Information System (INIS)

    Hurt, S.S.

    1986-11-01

    The Oak Ridge Research Reactor Safety Analysis was last updated via ORNL-4169, Vol. 2, Supplement 1, in May of 1978. Since that date, several changes have been effected through the change-memo system described below. While these changes have involved the cooling system, the electrical system, and the reactor instrumentation and controls, they have not, for the most part, presented new or unreviewed safety questions. However, some of the changes have been based on questions or recommendations stemming from safety reviews or from reactor events at other sites. This paper discusses those changes which were judged to be safety related and which include revisions to the syphon-break system and changes related to seismic considerations which were very recently completed. The maximum hypothetical accident postulated in the original safety analysis requires dynamic containment and filtered flow for compliance with 10CFR100 limits at the site boundary

  16. Geologic framework and hydrogeologic characteristics in the southern part of the Rancho Diana Natural Area, northern Bexar County, Texas, 2008-10

    Science.gov (United States)

    Clark, Allan K.; Morris, Robert R.

    2011-01-01

    The area designated by the city of San Antonio as the Rancho Diana Natural Area is in northern Bexar County, near San Antonio, Texas. During 2008-10, the U.S. Geological Survey, in cooperation with the city of San Antonio, documented the geologic framework and mapped the hydrogeologic characteristics for the southern part of the Rancho Diana Natural Area. The geologic framework of the study area and its hydrogeologic characteristics were documented using field observations and information from previously published reports. Many of the geologic and hydrogeologic features were found by making field observations through the dense vegetation along gridlines spaced approximately 25 feet apart and documenting the features as they were located. Surface geologic features were identified and hydrogeologic features such as caves, sinkholes, and areas of solutionally enlarged porosity were located using hand-held Global Positioning System units. The location data were used to create a map of the hydrogeologic subdivisions and the location of karst features. The outcrops of the Edwards and Trinity aquifer recharge zones were mapped by using hydrogeologic subdivisions modified from previous reports. All rocks exposed within the study area are of sedimentary origin and Lower Cretaceous in age. The valley floor is formed in the cavernous member of the upper Glen Rose Limestone of the Trinity Group. The hills are composed of the basal nodular member, dolomitic member, Kirschberg evaporite member, and grainstone member of the Kainer Formation of the Edwards Group. Field observations made during this study of the exposed formations and members indicate that the formations and members typically are composed of mudstones, wackestones, packstones, grainstones, and argillaceous limestones, along with marls. The upper Glen Rose Limestone is approximately 410 to 450 feet thick but only the upper 70 feet is exposed in the study area. The Kainer Formation is approximately 255 feet thick in

  17. Loss of coolant analysis for the tower shielding reactor 2

    International Nuclear Information System (INIS)

    Radcliff, T.D.; Williams, P.T.

    1990-06-01

    The operational limits of the Tower Shielding Reactor-2 (TSR-2) have been revised to account for placing the reactor in a beam shield, which reduces convection cooling during a loss-of-coolant accident (LOCA). A detailed heat transfer analysis was performed to set operating time limits which preclude fuel damage during a LOCA. Since a LOCA is survivable, the pressure boundary need not be safety related, minimizing seismic and inspection requirements. Measurements of reactor component emittance for this analysis revealed that aluminum oxidized in water may have emittance much higher than accepted values, allowing higher operating limits than were originally expected. These limits could be increased further with analytical or hardware improvements. 5 refs., 7 figs

  18. Desempenho de cordeiros terminados em confinamento, consumindo silagens de milho de grãos com alta umidade ou grãos de milho hidratados em substituição aos grãos de milho seco da dieta

    Directory of Open Access Journals (Sweden)

    Reis Wagner dos

    2001-01-01

    Full Text Available O experimento foi conduzido para avaliar o uso dos grãos de milho em diferentes formas (grãos de milho secos, silagem de grãos de milho hidratado e silagem de grãos de milho úmido sobre o desempenho de cordeiros terminados em confinamento. Foram usados 60 cordeiros (machos e fêmeas, distribuídos aleatoriamente em cinco tratamentos com doze repetições e alimentados com dietas isoprotéicas e isoenergéticas, em diferentes tratamentos: T1 (silagem de grãos de milho hidratados - SMGH, T2 (Grãos de milho seco - GMS, T3 (50% SGMH + 50% GMS, T4 (silagem de grãos de milho úmidos - SGMU e T5 (50% SGMU + 50% GMS. O volumoso utilizado foi feno de aveia. Foram avaliados ganho de peso diário e conversão alimentar aos 28, 56 e 73 dias de confinamento. A dieta com substituição total dos grãos de milho seco por silagem de grãos de milho úmidos apresentou maior ganho de peso aos 73 dias em relação àqueles obtidos aos 56 e 28 dias de confinamento. Este fato pode ser explicado pela melhor digestibilidade apresentada pelas silagens, atribuída à gelatinização que o amido sofre durante o processo. Assim, a silagem de grãos úmidos pode ser usada com eficácia em dietas para cordeiros.

  19. La historia sacra del Santísimo Sacramento contra las heregias destos tiempos"An iconographic study of the engravings illustrating the work

    Directory of Open Access Journals (Sweden)

    Calvo Portela, Juan Isaac

    2014-01-01

    Full Text Available En este artículo se hace un estudio iconográfico de las dos estampas que ilustran el libro del dominico fray Alonso de Ribera, La Historia Sacra del Santissimo Sacramento contra las heregias destos tiempos, editado por Luis Sánchez en Madrid en 1626. En dichas estampas se plasman dos aspectos que van a ser fundamentales de la religiosidad contrarreformista española del siglo XVII, la defensa a ultranza de la Eucaristía y la lucha contra la herejía. In this article is made an iconographic study of the two prints that illustrate the book of the Dominican Fray Alonso de Ribera, La Historia Sacra del Santissimo Sacramento contra las heregias destos tiempos, edited by Luis Sanchez in Madrid in 1626. In these prints are reflected two aspects that are going to be essential on the religiosity Spanish Counterreform of the seventeenth century, the stubborn defense of the Eucharist and the fight against heresy.

  20. Dalhousie SLOWPOKE-2 reactor: A nuclear analytical chemistry facility

    International Nuclear Information System (INIS)

    Chatt, A.; Holzbecher, J.

    1990-01-01

    SLOWPOKE is an acronym for Safe Low POwer Kritical Experiment. The SOWPOKE-2 is a compact, inherently safe, swimming-pool-type reactor designed by the Atomic Energy of Canada Limited for neutron activation analysis (NAA) and isotope production. The Dalhousie University SLOWPOKE-2 reactor (DUSR) has been operating since 1976; a large beryllium reflector was added in 1986 to extend its lifetime by another 8 to 10 yr. The DUSR is generally operated at half-power with a maximum thermal flux of 1.1 x 10 12 n/cm 2 ·s in the inner pneumatic sites and that of 5.4 x 10 11 n/cm 2 ·s in the outer sites. Despite this comparatively low flux, SLOWPOKE-2 reactors have many beneficial features that are continuously being exploited at the DUSR facility for developing nuclear analytical methods for fundamental as well as applied studies. Although NAA is a well-established analytical technique, much of the activation analysis being performed in most facilities has been limited to methods using fairly long-lived nuclides. The approach at the DUSR facility has been to utilize the highly homogeneous, stable, and reproducible neutron flux to develop NAA methods based on short-lived nuclides. SLOWPOKE reactors have a fairly high epithermal neutron flux, which is being advantageously used for determining several trace elements in complex matrices. Radiochemical NAA (RNAA) methods using coprecipitation, distillation, and ion-exchange separations have been used for the determination of very low levels of several elements in biological materials

  1. EFFECT OF DRY COW THERAPY DRUGS ON PHAGOCYTOSIS RATES EFEITO DE MEDICAMENTOS INDICADOS PARA O TRATAMENTO DE MASTITE BOVINA NO PERÍODO SECO SOBRE OS ÍNDICES DE FAGOCITOSE

    Directory of Open Access Journals (Sweden)

    Alice Maria Melville Paiva Della Libera

    2009-07-01

    Full Text Available The dry period is considered to be a phase when cows are very vulnerable to mastitis and phagocytosis mechanisms are specially important at this moment. The objective of the present trial was to evaluate the influence of dry cow therapy drugs available in the market on the phagocytic function of leukocytes obtained from cow milk. In order to do that, paired milk samples negative in bacteriological examination were submitted to in vitro phagocytosis test, after they were exposed to solutions of the following drugs: anhydrous cephalonium (M1, Gentamicin (M2, Benzylpenicillin procaine associated with Nafcillin and Dihydrostreptomycin (M3 and Cloxacillin benzathine (M4. Mean phagocytosis rates of control samples and of cells submitted to treatments M1 and M3 were, respectively, (58.88% ± 12.04, (64.87% ± 15.36 and (65.14% ± 17.96 there were no differences among these samples, as well as in the comparison with the control group. Mean phagocytosis rate obtained in cells submitted to treatment M4 (46.90% ± 22.08 was lower than that of the control group, and than that of cells submitted to treatments M1 and M3. On the other hand, mean phagocytosis rate of cells submitted to treatment M2 (0.68% ± 1.63 was lower than that observed in the control group, and than that of all other treatments. These results show that the use of drugs available for dry cow therapy may no be totally innocuous for the host.

    KEY WORDS: Dry period, mastitis, phagocytosis, treatment.
    O período seco é considerado uma fase da lactação muito vulnerável à mastite, e os mecanismos de fagocitose são especialmente importantes nessa etapa. Para avaliar a influência de medicamentos indicados para o tratamento de mastite no período seco sobre a função fagocítica de leucócitos obtidos do leite de vacas, foram utilizadas amostras pareadas de leite de vacas, negativas ao exame bacteriológico. Submeteram-se essas células à prova de fagocitose in vitro, ap

  2. Data for four geologic test holes in the Sacramento Valley, California

    Science.gov (United States)

    Berkstresser, C.F.; French, J.J.; Schaal, M.E.

    1985-01-01

    The report provides geological and geophysical data for four of seven test holes drilled as a part of the Central Valley Aquifer Project, which is part of the Regional Aquifer Systems Analysis. The holes were drilled with a rotary well drilling machine to depths of 900 feet in the southwestern part of the Sacramento Valley in Solano and Yolo Counties. Geologic data for each well include lithology, texture, color, character of the contact, sorting, rounding, and cementation, determined from cuttings, cores, and sidewall covers. Fifty cores, 3 feet long, were obtained from each hole, and from eight to fourteen sidewall cores were collected. Geophysical data include a dual-induction log, spherically focused log (SFL), compensated neutron-formation density log, gamma-ray log, and a caliper log. These data are presented in four tables and on four plates. (USGS)

  3. FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative

    International Nuclear Information System (INIS)

    Greene, S.R.; Spellman, D.J.; Bevard, B.B.

    1996-09-01

    The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 2 of a four volume report, summarizes the results of these analyses for the CANDU reactor based plutonium disposition alternative

  4. FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative

    Energy Technology Data Exchange (ETDEWEB)

    Greene, S.R.; Spellman, D.J.; Bevard, B.B. [and others

    1996-09-01

    The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 2 of a four volume report, summarizes the results of these analyses for the CANDU reactor based plutonium disposition alternative.

  5. Dynamic simulation of the 2 MWt slowpoke heating reactor

    International Nuclear Information System (INIS)

    Tseng, C.M.; Lepp, R.M.

    1982-04-01

    A 2 MWt SLOWPOKE reactor, intended for commercial space heating, is being developed at the Chalk River Nuclear Laboratories. A small-signal dynamic simulation of this reactor, without closed-loop control, was developed. Basic equations were used to describe the physical phenomena in each kf the eight reactor subsystems. These equations were then linearized about the normal operation conditions and rearranged in a dimensionless form for implementation. The overall simulation is non-linear. Slow transient responses (minutes to days) of the simulation to both reactivity and temperature perturbations were measured at full power. In all cases the system reached a new steady state in times varying from 12 h to 250 h. These results illustrate the benefits of the inherent negative reactivity feedback of this reactor concept. The addition of closed-loop control using core outlet temperature as the controlled variable to move a beryllium reflector is also examined

  6. Distribution of energy of impulses of the modernized IBR-2 REACTOR

    International Nuclear Information System (INIS)

    Tayibov, L.A; Mehtiyeva, R.N.; )

    2011-01-01

    Full text: For the modernized IBR-2 reactor there are two main reasons causing fluctuations of energy of impulses [1,3] on low power of stochastic fluctuations, on the nominal - giving rise to fluctuations of external reactance. The fluctuations of pulse energy is quite significant (20%). They affect the dynamics of the reactor, the process of regulation, starting, as well as the work of the experimental apparatus, etc. It is clear that research of fluctuation of energy of impulses has special value for the IBR-2 type reactor. Sufficient information about the statistical properties of the reactor noise gives the density distribution of the energy pulse power. We used the usual procedure of statistical analysis of time series. Calculated pulse energy of density and the parameters of this distribution.

  7. Effects of Sex and Education on Cognitive Change Over a 27-Year Period in Older Adults: The Rancho Bernardo Study.

    Science.gov (United States)

    Reas, Emilie T; Laughlin, Gail A; Bergstrom, Jaclyn; Kritz-Silverstein, Donna; Barrett-Connor, Elizabeth; McEvoy, Linda K

    2017-08-01

    This study investigated how cognitive function changes with age and whether rates of decline vary by sex or education in a large, homogenous longitudinal cohort characterized by high participation rates, long duration of follow-up, and minimal loss to follow-up. Between 1988 and 2016, 2,225 community-dwelling participants of the Rancho Bernardo Study, aged 31 to 99 years at their initial cognitive assessment, completed neuropsychological testing approximately every 4 years, over a maximum 27-year follow-up. Linear mixed effects regression models defined sex-specific cognitive trajectories, adjusting for education and retest effects. Significant decline across all cognitive domains began around age 65 years and accelerated after age 80 years. Patterns of decline were generally similar between sexes, although men declined more rapidly than women on the global function test. Higher education was associated with slower decline on the tests of executive and global functions. After excluding 517 participants with evidence of cognitive impairment, accelerating decline with age remained for all tests, and women declined more rapidly than men on the executive function test. Accelerating decline with advancing age occurs across multiple cognitive domains in community-dwelling older adults, with few differences in rates of decline between men and women. Higher education may provide some protection against executive and global function decline with age. These findings better characterize normal cognitive aging, a critical prerequisite for identifying individuals at risk for cognitive impairment, and lay the groundwork for future studies of health and behavioral factors that affect age-related decline in this cohort. Copyright © 2017 American Association for Geriatric Psychiatry. Published by Elsevier Inc. All rights reserved.

  8. Prevalência de olho seco em portadores de hanseníase de um hospital-colônia em Goiânia Prevalence of dry eye in Hansen's disease patients from a colony hospital in Goiânia, Brazil

    Directory of Open Access Journals (Sweden)

    Karys Carvalho Frazão

    2005-08-01

    Full Text Available OBJETIVO: Determinar a prevalência de olho seco em hansenianos do Hospital de Dermatologia Sanitária de Goiânia. MÉTODOS: A amostra do presente estudo incluiu 70 hansenianos, do Hospital de Dermatologia Sanitária de Goiânia, e 30 controles, da Fundação Banco de Olhos de Goiás, ambos localizados em Goiânia-GO. Foram realizados exame oftalmológico e testes de Schirmer I, "break-up time" (BUT e rosa bengala em todos estes indivíduos em uma única avaliação. Para o diagnóstico de olho seco foi considerado o teste de Schirmer I menor ou igual a 5 mm e o rosa bengala grau II ou III, em pelo menos um olho. RESULTADOS: Quarenta e quatro (63,0% hansenianos eram do sexo masculino e 22 (73,3% controles, do sexo feminino (p=0,001. A idade média dos hansenianos foi de 61,1±12,5 anos e no grupo controle, 55,7±9,6 anos. Quinze (21,4% hansenianos e quatro (13,3% controles apresentaram diagnóstico de olho seco (p=0,429. A forma virchowiana (HV (74,2% da hanseníase foi a mais prevalente e o olho seco (66,7% foi mais freqüente nesta forma clínica da doença. CONCLUSÃO: A prevalência de olho seco foi maior no grupo de hansenianos, apesar de não ter havido diferença significativa.PURPOSE: To determine the prevalence of dry eye in Hansen's disease patients from the "Hospital de Dermatologia Sanitária de Goiânia". METHODS: The sample of the present study included 70 patients with Hansen's disease, from the "Hospital de Dermatologia Sanitária de Goiânia", and 30 controls, from the "Fundação Banco de Olhos de Goiás", both located in Goiânia-GO, Brazil. Ophthalmologic examination and Schirmer I, break-up time (BUT and rose Bengal staining tests were carried out for all patients in a single evaluation. For the diagnosis of dry eye the Schirmer I equal or less than 5 mm and rose Bengal grade II or III, in at least one eye were considered. RESULTS: Forty-four (63.0% patients with Hansen's disease were male and 22 (73.3% controls were female

  9. Digital Mapping Techniques '10-Workshop Proceedings, Sacramento, California, May 16-19, 2010

    Science.gov (United States)

    Soller, David R.; Soller, David R.

    2012-01-01

    The Digital Mapping Techniques '10 (DMT'10) workshop was attended by 110 technical experts from 40 agencies, universities, and private companies, including representatives from 19 State geological surveys (see Appendix A). This workshop, hosted by the California Geological Survey, May 16-19, 2010, in Sacramento, California, was similar in nature to the previous 13 meetings (see Appendix B). The meeting was coordinated by the U.S. Geological Survey's (USGS) National Geologic Map Database project. As in the previous meetings, the objective was to foster informal discussion and exchange of technical information. It is with great pleasure that I note that the objective was again successfully met, as attendees continued to share and exchange knowledge and information, and renew friendships and collegial work begun at past DMT workshops. At this meeting, oral and poster presentations and special discussion sessions emphasized (1) methods for creating and publishing map products ("publishing" includes Web-based release); (2) field data capture software and techniques, including the use of LiDAR; (3) digital cartographic techniques; (4) migration of digital maps into ArcGIS Geodatabase format; (5) analytical GIS techniques; and (6) continued development of the National Geologic Map Database.

  10. Evaluating the Aquatic Habitat Potential of Flooded Polders in the Sacramento-San Joaquin Delta

    Directory of Open Access Journals (Sweden)

    John R. Durand

    2017-12-01

    Full Text Available https://doi.org/10.15447/sfews.2017v15iss4art4Large tracts of land in the Sacramento-San Joaquin Delta are subsided due to agricultural practices, creating polders up to 10 m below sea level that are vulnerable to flooding. As protective dikes breach, these become shallow, open water habitats that will not resemble any historical state. I investigated physical and biotic drivers of novel flooded polder habitat, using a Native Species Benefit Index (NSBI to predict the nature of future Delta ecosystems. Results suggest that flooded polders in the north Delta will have the ecology and fish community composition of a tidal river plain, those in the Cache-Lindsey Complex will have that of a tidal backwater, those in the confluence of the Sacramento and San Joaquin Rivers a brackish estuary, and those in the south Delta a fresh water lake. Flooded east-side Delta polders will likely be a transitional zone between south Delta lake-like ecosystems and north Delta tidal river plains. I compared each regional zone with the limited available literature and data on local fish assemblies to find support for NSBI predictions. Because flood probabilities and repair prioritization analyses suggest that polders in the south Delta are most likely to flood and be abandoned, without extensive intervention, much of the Delta will become a freshwater lake ecosystem, dominated by alien species. Proactive management of flooded tracts will nearly always hedge risks, save money and offer more functional habitats in the future; however, without proper immediate incentives, it will be difficult to encourage strong management practices.

  11. Equipment for thermal neutron flux measurements in reactor R2

    Energy Technology Data Exchange (ETDEWEB)

    Johansson, E; Nilsson, T; Claeson, S

    1960-04-15

    For most of the thermal neutron flux measurements in reactor R2 cobalt wires will be used. The loading and removal of these wires from the reactor core will be performed by means of a long aluminium tube and electromagnets. After irradiation the wires will be scanned in a semi-automatic device.

  12. A conceptual design of LIB fusion reactor: UTLIF(2)

    International Nuclear Information System (INIS)

    Madarame, Haruki; Kondo, Shunsuke; Iwata, Shuichi; Oka, Yoshiaki; Miya, Kenzo.

    1984-01-01

    UTLIF(2) is a conceptual design study on a light ion beam driven fusion reactor based on a concept of rod-bundle blanket. Survivability and maintainability of the first wall and the blanket are regarded as of major importance in the design. The blanket rod is composed of a thick tube which has enough stiffness, a thin wrapping wall which receives high heat flux, and liquid lithium which breeds tritium and removes generated heat. The rod can be pulled out from the outside of the reactor vessel, hence the replacement is very easy. Nuclear and thermal analysis have been made and the performance of the reactor has been shown to be satisfactory. (author)

  13. The BR2 materials testing reactor. Past, ongoing and under-study upgradings

    Energy Technology Data Exchange (ETDEWEB)

    Baugnet, J M; Roedt, Ch de; Gubel, P; Koonen, E [Centre d' Etude de I' Energie Nucleaire, Studiecentrum voor Kernenergie, C.E.N./S.C.K., Mol (Belgium)

    1990-05-01

    The BR2 reactor (Mol, Belgium) is a high-flux materials testing reactor. The fuel is 93% {sup 235}U enriched uranium. The nominal power ranges from 60 to 100 MW. The main features of the design are the following: 1) maximum neutron flux, thermal: 1.2 x 10{sup 15} n/cm{sup 2} s; fast (E > 0.1 MeV) : 8.4 x 10{sup 14} n /cm{sup 2} s; 2) great flexibility of utilization: the core configuration and operation mode can be adapted to the experimental loading; 3) neutron spectrum tailoring; 4) availability of five 200 mm diameter channels besides the standard channels (84 mm diameter); 5) access to the top and bottom covers of the reactor authorizing the irradiation of loops. The reactor is used to study the behaviour of fuel elements and structural materials intended for future nuclear power stations of several types (fission and fusion). Irradiations are carried out in connection with performance tests up to very high burn-up or neutron fluence as well as for safety experiments, power cycling experiments, and generally speaking, tests under off-normal conditions. Irradiations for nuclear transmutation (production of high specific activity radio-isotopes and transplutonium elements), neutron-radiography, use of beam tubes for physics studies, and gamma irradiations are also carried out. The BR2 is used in support of Belgian programs, at the request of utilities, industry and universities and in the framework of international agreements. The paper reviews the past and ongoing upgrading and enhancement of reactor capabilities as well as those under study or consideration, namely with regard to: reactor equipment, fuel elements, irradiation facilities, reactor operation conditions and long-term strategy. (author)

  14. TiO2 Solar Photocatalytic Reactor Systems: Selection of Reactor Design for Scale-up and Commercialization—Analytical Review

    Directory of Open Access Journals (Sweden)

    Yasmine Abdel-Maksoud

    2016-09-01

    Full Text Available For the last four decades, viability of photocatalytic degradation of organic compounds in water streams has been demonstrated. Different configurations for solar TiO2 photocatalytic reactors have been used, however pilot and demonstration plants are still countable. Degradation efficiency reported as a function of treatment time does not answer the question: which of these reactor configurations is the most suitable for photocatalytic process and optimum for scale-up and commercialization? Degradation efficiency expressed as a function of the reactor throughput and ease of catalyst removal from treated effluent are used for comparing performance of different reactor configurations to select the optimum for scale-up. Comparison included parabolic trough, flat plate, double skin sheet, shallow ponds, shallow tanks, thin-film fixed-bed, thin film cascade, step, compound parabolic concentrators, fountain, slurry bubble column, pebble bed and packed bed reactors. Degradation efficiency as a function of system throughput is a powerful indicator for comparing the performance of photocatalytic reactors of different types and geometries, at different development scales. Shallow ponds, shallow tanks and fountain reactors have the potential of meeting all the process requirements and a relatively high throughput are suitable for developing into continuous industrial-scale treatment units given that an efficient immobilized or supported photocatalyst is used.

  15. Análise da transição entre dias secos e chuvosos por meio da cadeia de Markov de terceira ordem Analysis of the transition between dry and wet days through third-order Markov chains

    Directory of Open Access Journals (Sweden)

    Thadeu Keller Filho

    2006-09-01

    Full Text Available O objetivo deste trabalho foi verificar se as ocorrências de dias secos e chuvosos são condicionalmente dependentes da seqüência dos três dias secos e chuvosos anteriores, numa zona pluviometricamente homogênea, por meio da cadeia não-homogênea de Markov de terceira ordem. Os resultados mostraram que as probabilidades diárias de transição podem ser adequadamente estimadas, com base em dados agregados bimestralmente, seguidas de interpolação por meio de funções sinusoidais. Além disso, evidenciou-se que, naquela zona, as ocorrências diárias de chuva são condicionalmente dependentes da seqüência de dias secos e chuvosos nos três dias anteriores. A cadeia não-homogênea de Markov de terceira ordem é um importante instrumento para a análise da dependência entre as seqüências de dias secos e chuvosos em determinadas regiões.The aim of this work was to verify if the occurrence of dry and wet days are conditionally dependent on the sequences of the dry and wet three preceding days, in a rainfall homogeneous area, using the nonhomogeneous third-order Markov chains. The results showed that daily transition probabilities can be properly estimated from two-month aggregate data, and then adjusted by means of sinusoidal functions. Besides, it was evidenced that everyday rain events in that area are conditionally dependent on the sequences of the dry and wet three days previous to occurrences. The third-order nonhomogeneous Markov chains are an important instrument for the analysis of the dependence between sequences of dry and wet days in certain areas.

  16. Planned Scientific programs around the Triga Mark 2 Reactor

    International Nuclear Information System (INIS)

    Majah, M Ibn.

    2007-01-01

    Full text: Nuclear techniques have been introduced to Morocco since the sixties. After the energy crisis of 1973, Morocco decides to create the National Center for Energy Sciences and Nuclear Techniques (CNESTEN) under the supervision of the Ministry of high Education and Research, with a research commercial and support vocation. CNESTEN is in charge of promoting nuclear application, to act as technical support for the authorities and to prepare the technological basis for nuclear power option. In 1998, CNESTEN started the construction of Nuclear Research Centre. The on going activities cover many sectors : earth and environmental sciences, high energy physics, safety and security, waste management. In 2001, CNESTEN started the construction of a 2MW TRiga Mark 2 Reactor, with the possibility to increase the power to 3 MW. The construction was achieved in January 2007. The operation of the reactor is expected for April 2007. The program of the utilization of the reactor was established with th contribution of the university and with the assistance of IAEA. Some of the experimental set-up installed around the reactor have been designed. CNESTEN has developed cooperation with Nuclear research centres from other countries and is receiving visitors and trainees mainly through the IAEA [fr

  17. Power noise spectrum classification in the problem of the IBR-2 reactor

    International Nuclear Information System (INIS)

    Bargel, M.; Kitowski, J.; Pepelyshev, Yu.N.

    1988-01-01

    The classification spectrum results of random fluctuations in the IBR-2 energy pulse are presented. The work is performed for the application of the obtained results to the reactor diagnostics and the study of its noise uncontrolled states. For classification of the spectra the method of pattern recognition based upon the ISODATA heuristic algorithm is used. It is shown that a set of noise uncontrolled reactor states, registered during the reactor operation period at power of 0.4-2 MVt with the first variant of moving reflector (1983-1986) is formed into 4(5) most typical states. Each of the states corresponds to the general conditions of the reactor core cooling and provides the normal work of the moving reflector. However, these states differ in coolant flow, power level and peculiarities of the moving reflector rotation regime. One type of anomal power noise, connected with some disorder in the moving reflctor work, is isolated. This work also presents the possibility of control over the state of moving reflectors according to the change in the amplitude of power oscillations at some frequences. The reactor noise classification results can be used as the data bank for the IBR-2 reactor diagnostic system

  18. Guaianolides and a seco-eudesmane from the resinous exudates of cushion bush (Leucophyta brownii) and evaluation of their cytostatic and anti-inflammatory activity

    DEFF Research Database (Denmark)

    Gade Hyldgaard, Mette; Purup, Stig; Bond, Andrew David

    2015-01-01

    A detailed phytochemical investigation of a dichloromethane extract of the resinous exudates of the cushion bush plant (Leucophyta brownii) resulted in the isolation of the new 8,12-guaianolides leucophytalins A (5) and B (6), the new 1,10-seco-eudesmane leucophytalin C (10), six rare 8......,12-guaianolides (1–4, 7, and 8), and the xanthanolide tomentosin (9). The structures of all isolated compounds were elucidated on the basis of spectroscopic and spectrometric analyses. The structures of compounds isolated in crystalline form, including leucophytalins A and C, were further confirmed by X....../mL for thromboxane B2 and prostaglandin E2 production, respectively. The isolated compounds were evaluated for their cytostatic activity against MCF-7 and HT-29 cells (1, 3–10) and their anti-inflammatory activity against RAW 264.7 cells (1–10). All isolated compounds are most likely derived from (+)-germacrene A...

  19. Diseño del proceso de obtención de trozos secos de carambola (averroha carambola l.) tratados osmóticamente

    OpenAIRE

    Castillo Ortiz, Maria Eugenia; Cornejo Z., Fabiola

    2009-01-01

    En el presente trabajo se diseñó la línea de proceso para obtener trozos secos de carambola tratados osmóticamente, mostrando la utilidad industrial que posee la carambola para la elaboración de productos que puedan ser exportados al mercado extranjero con excelentes características organolépticas y condiciones de estabilidad en percha óptimas. Los experimentos realizados sirvieron para establecer la cinética de deshidratación osmótica, analizada a 3 concentraciones de sacarosa (40 ºBrix,...

  20. Research reactor FR2 - 20 years chemical and radiochemical measurements

    International Nuclear Information System (INIS)

    Feuerstein, H.; Graebner, H.; Oschinski, J.; Hoffmann, W.; Beyer, J.

    1986-09-01

    The FR2 has been a D 2 O cooled and moderated research reactor with a thermal output of 44 MW. It was in operation from 1961 to 1981. Because of the operating conditions of the reactor, only a small number of routine measurements were performed. For these however special techniques had to be developed. During the 20 years of operation a number of special events occured or have been observed, sometimes with very amazing results, e.g. the 'aceton effect'. This report describes the chemical and radiochemical conditions of the reactor systems, as well as the results of the surveilance work. Not described are measurements for the many experiments. The last chapter gives in a short form a description of the most unusual events and observations. (orig.) [de

  1. Venting krypton-85 from the Three Mile Island Unit 2 reactor building

    International Nuclear Information System (INIS)

    Burton, H.M.

    1981-01-01

    To permit the less restricted access to the reactor building necessary to maintain instrumentation and equipment, and to proceed towad the total decontamination of the facility, General Public Utilities, operators of the facility referred to hereafter as GPU, asked the United States Nuclear Regulatory Commission, or NRC, for permission to remove the 85 Kr from the reactor building by venting it to the environment. GPU supported their request with the Safety Analysis and Environmental Assessment Report on the proposed reactor building venting plan. On June 12, 1980, after seven months of licensing deliberations and numerous public hearings, the NRC granted GPU's request. The actual venting took place between June 28 and July 11, 1980. This report presents an overview of the detailed effort involved in the TMI-2 reactor building venting program. The findings reported here are condensed from a published report entitled TMI-2 Reactor Building Purge--Kr-85 Venting

  2. Research on economics and CO2 emission of magnetic and inertial fusion reactors

    International Nuclear Information System (INIS)

    Mori, Kenjiro; Yamazaki, Kozo; Oishi, Tetsutarou; Arimoto, Hideki; Shoji, Tatsuo

    2011-01-01

    An economical and environment-friendly fusion reactor system is needed for the realization of attractive power plants. Comparative system studies have been done for magnetic fusion energy (MFE) reactors, and been extended to include inertial fusion energy (IFE) reactors by Physics Engineering Cost (PEC) system code. In this study, we have evaluated both tokamak reactor (TR) and IFE reactor (IR). We clarify new scaling formulas for cost of electricity (COE) and CO 2 emission rate with respect to key design parameters. By the scaling formulas, it is clarified that the plant availability and operation year dependences are especially dominant for COE. On the other hand, the parameter dependences of CO 2 emission rate is rather weak than that of COE. This is because CO 2 emission percentage from manufacturing the fusion island is lower than COE percentage from that. Furthermore, the parameters dependences for IR are rather weak than those for TR. Because the CO 2 emission rate from manufacturing the laser system to be exchanged is very large in comparison with CO 2 emission rate from TR blanket exchanges. (author)

  3. Development of a TiO2-coated optical fiber reactor for water decontamination

    International Nuclear Information System (INIS)

    Danion, A.

    2004-09-01

    The objective of this study was to built and to study a photo-reactor composed by TiO 2 -coated optical fibers for water decontamination. The physico-chemical characteristics and the optical properties of the TiO 2 coating were first studied. Then, the influences of different parameters as the coating thickness, the coating length and the coating volume were investigated both on the light transmission in the TiO 2 - coated fiber and on the photo-catalytic activity of the fiber for a model compound (malic acid). The photo-catalytic degradation of malic acid was optimized using the experimental design methodology allowing to build a multi-fiber reactor comprising 57 optical fibers. The photo-degradation of malic acid was conducted in the multi-fiber reactor and it was demonstrated that the multi-fiber reactor was more efficient than the single-fiber reactor at the same fibers density. Finally, the multi-fiber reactor was applied to the photo-degradation of a fungicide, called fenamidone, and a degradation pathway was proposed. (author)

  4. Tuning the light in senior care: Evaluating a trial LED lighting system at the ACC Care Center in Sacramento, CA

    Energy Technology Data Exchange (ETDEWEB)

    Davis, Robert G.; Wilkerson, Andrea M.; Samla, Connie; Bisbee, Dave

    2016-08-31

    This report summarizes the results from a trial installation of light-emitting diode (LED) lighting systems in several spaces within the ACC Care Center in Sacramento, CA. The Sacramento Municipal Utility District (SMUD) coordinated the project and invited the U.S. Department of Energy (DOE) to document the performance of the LED lighting systems as part of a GATEWAY evaluation. DOE tasked the Pacific Northwest National Laboratory (PNNL) to conduct the investigation. SMUD and ACC staff coordinated and completed the design and installation of the LED systems, while PNNL and SMUD staff evaluated the photometric performance of the systems. ACC staff also track behavioral and health measures of the residents; some of those results are reported here, although PNNL staff were not directly involved in collecting or interpreting those data. The trial installation took place in a double resident room and a single resident room, and the corridor that connects those (and other) rooms to the central nurse station. Other spaces in the trial included the nurse station, a common room called the family room located near the nurse station, and the ACC administrator’s private office.

  5. LISTA COMENTADA DE LAS PLANTAS VASCULARES DEL ENCLAVE SECO INTERANDINO DE LA TATACOA (HUILA, COLOMBIA

    Directory of Open Access Journals (Sweden)

    FIGUEROA-C. YISELA

    2007-12-01

    Full Text Available Se presenta el inventario florístico del enclave seco interandino de La Tatacoa (vallede la parte alta del río Magdalena, Huila, Colombia. Se encontraron 223 especies,distribuidas en 170 géneros y 60 familias. A nivel florístico, la familia Leguminosaees la más diversificada con 36 especies y 28 géneros, seguida por Poaceae (20/15,Euphorbiaceae (13/6, Asteraceae (10/10 y Cactaceae (8/7. El hábito de crecimientopredominante en términos de riqueza de especies fue el de las hierbas, seguido porlos hábitos leñosos (árboles, arbustos y sufrútices, y el mayor número de especiesse encontró en las zonas de áreas abiertas y en las riberas de quebradas. Se registrancuatro hallazgos corológicos interesantes, incluyendo el primer registro de Sennauniflora para Colombia.

  6. TMI-2 reactor-vessel head removal and damaged-core-removal planning

    International Nuclear Information System (INIS)

    Logan, J.A.; Hultman, C.W.; Lewis, T.J.

    1982-01-01

    A major milestone in the cleanup and recovery effort at TMI-2 will be the removal of the reactor vessel closure head, planum, and damaged core fuel material. The data collected during these operations will provide the nuclear power industry with valuable information on the effects of high-temperature-dissociated coolant on fuel cladding, fuel materials, fuel support structural materials, neutron absorber material, and other materials used in reactor structural support components and drive mechanisms. In addition, examination of these materials will also be used to determine accident time-temperature histories in various regions of the core. Procedures for removing the reactor vessel head and reactor core are presented

  7. Proceedings of the 1992 topical meeting on advances in reactor physics. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    1992-04-01

    This document, Volume 2, presents proceedings of the 1992 Topical Meeting on Advances in Reactor Physics on March 8--11, 1992 at Charleston, SC. Session topics were as follows: Transport Theory; Fast Reactors; Plant Analyzers; Integral Experiments/Measurements & Analysis; Core Computational Systems; Reactor Physics; Monte Carlo; Safety Aspects of Heavy Water Reactors; and Space-Time Core Kinetics. The individual reports have been cataloged separately. (FI)

  8. Fissile fuel production and usage of thermal reactor waste fueled with UO2 by means of hybrid reactor system

    International Nuclear Information System (INIS)

    Ipek, O.

    1997-01-01

    The use of Fast Breeder Reactors to produce fissile fuel from nuclear waste and the operation of these reactors with a new neutron source are becoming today' topic. In the thermonuclear reactors, it is possible to use 2.45-14.1 MeV - neutrons which can be obtained by D-T, D-D Semicatalyzed (D-D) and other fusion reactions. To be able to do these, Hybrid Reactor System, which still has experimental and theoretical studies, have to be taken into consideration.In this study, neutronic analysis of hybrid blanket with grafit reflector, is performed. D-T driven fusion reaction is surrounded by UO 2 fuel layer and the production of ''2''3''9Pu fissile fuel from waste ''2''3''8U is analyzed. It is also compared to the other possible fusion reactions. The results show that 815.8 kg/year ''2''3''8Pu with D-T reaction and 1431.6 kg/year ''2''3''8Pu with semicatalyzed (D-D) reaction can be produced for 1000 MW fusion power. This means production of 2.8/ year and 4.94/ year LWR respectively. In addition, 1000 MW fusion flower is is multiplicated to 3415 MW and 4274 MW for D-T and semicatalyzed (D-D) reactions respectively. The system works subcritical and these values are 0.4115 and 0.312 in order. The calculations, ANISN-ORNL code, S 16 -P 3 approach and DLC36 data library are used

  9. A theoretical analysis of methanol synthesis from CO2 and H2 in a ceramic membrane reactor

    NARCIS (Netherlands)

    Gallucci, F.; Basile, A.

    2007-01-01

    In this theoretical work the CO2 conversion into methanol in both a traditional reactor (TR) and a membrane reactor (MR) is considered. The purpose of this study was to investigate the possibility of increasing CO2 conversion into methanol with respect to a TR. A zeolite MR, able to combine

  10. Cronos 2: a neutronic simulation software for reactor core calculations

    International Nuclear Information System (INIS)

    Lautard, J.J.; Magnaud, C.; Moreau, F.; Baudron, A.M.

    1999-01-01

    The CRONOS2 software is that part of the SAPHYR code system dedicated to neutronic core calculations. CRONOS2 is a powerful tool for reactor design, fuel management and safety studies. Its modular structure and great flexibility make CRONOS2 an unique simulation tool for research and development for a wide variety of reactor systems. CRONOS2 is a versatile tool that covers a large range of applications from very fast calculations used in training simulators to time and memory consuming reference calculations needed to understand complex physical phenomena. CRONOS2 has a procedure library named CPROC that allows the user to create its own application environment fitted to a specific industrial use. (authors)

  11. Estimation of reservoir inflow in data scarce region by using Sacramento rainfall runoff model - A case study for Sittaung River Basin, Myanmar

    Science.gov (United States)

    Myo Lin, Nay; Rutten, Martine

    2017-04-01

    The Sittaung River is one of four major rivers in Myanmar. This river basin is developing fast and facing problems with flood, sedimentation, river bank erosion and salt intrusion. At present, more than 20 numbers of reservoirs have already been constructed for multiple purposes such as irrigation, domestic water supply, hydro-power generation, and flood control. The rainfall runoff models are required for the operational management of this reservoir system. In this study, the river basin is divided into (64) sub-catchments and the Sacramento Soil Moisture Accounting (SAC-SMA) models are developed by using satellite rainfall and Geographic Information System (GIS) data. The SAC-SMA model has sixteen calibration parameters, and also uses a unit hydrograph for surface flow routing. The Sobek software package is used for SAC-SMA modelling and simulation of river system. The models are calibrated and tested by using observed discharge and water level data. The statistical results show that the model is applicable to use for data scarce region. Keywords: Sacramento, Sobek, rainfall runoff, reservoir

  12. Set of rules SOR 2 reactor site criteria

    International Nuclear Information System (INIS)

    1976-06-01

    The purpose of this set of rules is to describe criteria which guide the Director in his evaluation of the suitability of proposed sites for stationary power and testing reactors subject to SOR 2. (B.G.)

  13. Homogeneous fast reactor benchmark testing of CENDL-2 and ENDF/B-6

    International Nuclear Information System (INIS)

    Liu Guisheng

    1995-01-01

    How to choose correct weighting spectrum has been studied to produce multigroup constants for fast reactor benchmark calculations. A correct weighting option makes us obtain satisfying results of K eff and central reaction rate ratios for nine fast reactor benchmark testings of CENDL-2 and ENDF/B-6. (4 tabs., 2 figs.)

  14. Implementing trials of complex interventions in community settings: the USC-Rancho Los Amigos pressure ulcer prevention study (PUPS).

    Science.gov (United States)

    Clark, Florence; Pyatak, Elizabeth A; Carlson, Mike; Blanche, Erna Imperatore; Vigen, Cheryl; Hay, Joel; Mallinson, Trudy; Blanchard, Jeanine; Unger, Jennifer B; Garber, Susan L; Diaz, Jesus; Florindez, Lucia I; Atkins, Michal; Rubayi, Salah; Azen, Stanley Paul

    2014-04-01

    Randomized trials of complex, non-pharmacologic interventions implemented in home and community settings, such as the University of Southern California (USC)-Rancho Los Amigos National Rehabilitation Center (RLANRC) Pressure Ulcer Prevention Study (PUPS), present unique challenges with respect to (1) participant recruitment and retention, (2) intervention delivery and fidelity, (3) randomization and assessment, and (4) potential inadvertent treatment effects. We describe the methods employed to address the challenges confronted in implementing PUPS. In this randomized controlled trial, we are assessing the efficacy of a complex, preventive intervention in reducing the incidence of, and costs associated with, the development of medically serious pressure ulcers in people with spinal cord injury. Individuals with spinal cord injury recruited from RLANRC were assigned to either a 12-month preventive intervention group or a standard care control group. The primary outcome is the incidence of serious pressure ulcers with secondary endpoints including ulcer-related surgeries, medical treatment costs, and quality of life. These outcomes are assessed at 12 and 24 months after randomization. Additionally, we are studying the mediating mechanisms that account for intervention outcomes. PUPS has been successfully implemented, including recruitment of the target sample size of 170 participants, assurance of the integrity of intervention protocol delivery with an average 90% treatment adherence rate, and enactment of the assessment plan. However, implementation has been replete with challenges. To meet recruitment goals, we instituted a five-pronged approach customized for an underserved, ethnically diverse population. In intervention delivery, we increased staff time to overcome economic and cultural barriers to retention and adherence. To ensure treatment fidelity and replicability, we monitored intervention protocol delivery in accordance with a rigorous plan. Finally, we

  15. Groundwater Monitoring Plan for the Reactor Technology Complex Operable Unit 2-13

    International Nuclear Information System (INIS)

    Richard P. Wells

    2007-01-01

    This Groundwater Monitoring Plan describes the objectives, activities, and assessments that will be performed to support the on-going groundwater monitoring requirements at the Reactor Technology Complex, formerly the Test Reactor Area (TRA). The requirements for groundwater monitoring were stipulated in the Final Record of Decision for Test Reactor Area, Operable Unit 2-13, signed in December 1997. The monitoring requirements were modified by the First Five-Year Review Report for the Test Reactor Area, Operable Unit 2-13, at the Idaho National Engineering and Environmental Laboratory to focus on those contaminants of concern that warrant continued surveillance, including chromium, tritium, strontium-90, and cobalt-60. Based upon recommendations provided in the Annual Groundwater Monitoring Status Report for 2006, the groundwater monitoring frequency was reduced to annually from twice a year

  16. Ontogenetic behavior and dispersal of Sacramento River white sturgeon, Acipenser transmontanus, with a note on body color

    Science.gov (United States)

    Kynard, B.; Parker, E.

    2005-01-01

    We studied Sacramento River white sturgeon, Acipenser transmontanus, in the laboratory to develop a conceptual model of ontogenetic behavior and provide insight into probable behavior of wild sturgeon. After hatching, free embryos initiated a low intensity, brief downstream dispersal during which fish swam near the bottom and were photonegative. The weak, short dispersal style and behavior of white sturgeon free embryos contrasts greatly with the intense, long dispersal style and behavior (photopositive and swimming far above the bottom) of dispersing free embryos of other sturgeon species. If spawned eggs are concentrated within a few kilometers downstream of a spawning site, the adaptive significance of the free embryo dispersal is likely to move fish away from the egg deposition site to avoid predation and reduce fish density prior to feeding. Larvae foraged on the open bottom, swam innate fish dispersal and post-dispersal rearing habitat, which is now highly altered by damming and reservoirs. Sacramento River white sturgeon has a two-step downstream dispersal by the free embryo and juvenile life intervals. Diel activity of all life intervals peaked at night, whether fish were dispersing or foraging. Nocturnal behavior is likely a response to predation, which occurs during both activities. An intense black-tail body color was present on foraging larvae, but was weak or absent on the two life intervals that disperse. Black-tail color may be an adaptation for avoiding predation, signaling among aggregated larvae, or both, but not for dispersal. ?? Springer 2005.

  17. GATEWAY Demonstrations: Tuning the Light in Senior Care: Evaluating a Trial LED Lighting System at the ACC Care Center in Sacramento, CA

    Energy Technology Data Exchange (ETDEWEB)

    Davis, Robert G. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wilkerson, Andrea M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Samla, Connie [Sacramento Municipal Utility District, Sacramento, CA (United States); Bisbee, Dave [Sacramento Municipal Utility District, Sacramento, CA (United States)

    2016-08-31

    The GATEWAY program documented the performance of tunable-white LED lighting systems installed in several spaces within the ACC Care Center, a senior-care facility in Sacramento, CA. The project results included energy savings and improved lighting quality, as well as other possible health-related benefits that may have been attributable, at least in part, to the lighting changes.

  18. Homogeneous fast reactor benchmark testing of CENDL-2 and ENDF/B-6

    International Nuclear Information System (INIS)

    Liu Guisheng

    1995-11-01

    How to choose correct weighting spectrum has been studied to produce multigroup constants for fast reactor benchmark calculations. A correct weighting option makes us obtain satisfying results of K eff and central reaction rate ratios for nine fast reactor benchmark testing of CENDL-2 and ENDF/B-6. (author). 8 refs, 2 figs, 4 tabs

  19. An experimental investigation of fission product release in SLOWPOKE-2 reactors - Data report

    International Nuclear Information System (INIS)

    Harnden, A.M.C.

    1995-09-01

    The results of an investigation into the release of fission products from SLOWPOKE-2 reactors fuelled with a highly-enriched uranium alloy core are detailed in Volume 1. This data report (Volume 2) contains plots of the activity concentrations of the fission products observed in the reactor container at the University of Toronto, Ecole Polytechnique and the Kanata Isotope Production Facility. Release rates from the reactor container water to the gas headspace are also included. (author)

  20. High School Graduate Participation Rates: Proportions of Sacramento Area High School Graduates Enrolled in Los Rios Community College District, Fall 1998-Fall 1994.

    Science.gov (United States)

    Los Rios Community Coll. District, Sacramento, CA. Office of Planning and Research.

    This report profiles the enrollment patterns of recent high school graduates of the Greater Sacramento Metropolitan Area who attend Los Rios colleges (California). This summary and the full data report provide the District and its colleges with research information on rates of participation by students who graduated from Los Rios Community College…

  1. Teleconexiones atmosféricas-oceánicas (océanos Pacífico y Atlántico moduladoras de veranos húmedos y secos en el Núcleo del Monzón de Norte América

    Directory of Open Access Journals (Sweden)

    Omar Llanes-Cárdenas

    2017-01-01

    Full Text Available En décadas recientes, la irregularidad de las precipitaciones ha tenido diversos efectos ambientales y socioeconómicos adversos a nivel mundial. El objetivo de este trabajo fue analizar la resolución de cuatro Modelos Climáticos Regionales (MCR’s forzados por ERA - Interim para capturar los monzones extremos húmedos y secos en el Núcleo del Monzón de Norte América (NMNA, considerando los mecanismos oceánicos del Pacífico y del Atlántico. De las bases de datos disponibles en la red y para el período 1990 - 2008, se obtuvo: (1 promedio de las observaciones (obs media después de haber obtenido 4 conjuntos de datos de precipitación observados: UDel, CLICOM, GPCP y CRU, (2 d el Experimento Regional Coordinado de Reducción de Escala (COR DEX - de Norte América (NA se obtuvieron cuatro MCR’s forzados por ERA - Interim : RegCM4 ( Reg1 y Reg2, HadGEM3 - RA, RCA3.5 y REMO, (3 número e intensidad de los huracanes del Pacífico y (4 cálculo de las anomalías del Jet de Niveles Bajos del Caribe (CLLJ , Varianza Filtrada (VF, Oscilación Decadal del Pacífico (PDO y Oscilación Multidecadal del Atlántico (AMO. Se seleccionaron dos monzones extremos: uno húmedo (1990 y otro seco (2005. Se aplicó una prueba de normalidad de Shapiro Wilk a los datos a es tudiar. Se calculó una correlación de Pearson y una prueba de hipótesis con nivel de confianza de 95 % (P < 0.05 y 99 % (P < 0.01 entre los modelos, Era - Interim, las observaciones y los índices oceánicos. Sin considerar los índices oceánicos, HadGEM3 - RA y ERA - Interim capturan de mejor manera la precipitación en los monzones húmedos, en tanto que ERA - Interim y Reg1 resultaron ser mejores para capturar la precipitación para monzones secos. El monzón de 1990 presentó casi el doble de precipitación que el 200 5. Esta anomalía húmeda al parecer se asocia con la ocurrencia de 16 huracanes cerca del Golfo de California en 1990, lo que contrasta con el 2005, cuando solo se

  2. Safety assessments relating to the use of new fuels in research reactors: application to the case of FRM 2 reactor fuel

    International Nuclear Information System (INIS)

    Abou Yehia, H.; Bars, G.; Tran Dai

    2001-01-01

    After giving a brief reminder of the procedure applied in France for the licensing of the use of a new fuel type or design in a research reactor, we outline the main safety aspects associated with such a modification. Finally, by way of an example, we focus on the safety assessment relating to the IRIS irradiation device used in SILOE reactor, in particular for the qualification of the fuel dedicated to FRM II reactor of the Technical University of Munich. This qualification was carried out on a U 3 Si 2 fuel plate enriched to about 90 % in weight of 235 U and containing 1.5 g of uranium per cm 3 . The evaluation performed by the IPSN for GRS did not call into question the choice of U 3 Si 2 fuel plates for the FRM-II reactor. (authors)

  3. Thermal neutron flux distribution in ET-RR-2 reactor thermal column

    Directory of Open Access Journals (Sweden)

    Imam Mahmoud M.

    2002-01-01

    Full Text Available The thermal column in the ET-RR-2 reactor is intended to promote a thermal neutron field of high intensity and purity to be used for following tasks: (a to provide a thermal neutron flux in the neutron transmutation silicon doping, (b to provide a thermal flux in the neutron activation analysis position, and (c to provide a thermal neutron flux of high intensity to the head of one of the beam tubes leading to the room specified for boron thermal neutron capture therapy. It was, therefore, necessary to determine the thermal neutron flux at above mentioned positions. In the present work, the neutron flux in the ET-RR-2 reactor system was calculated by applying the three dimensional diffusion depletion code TRITON. According to these calculations, the reactor system is composed of the core, surrounding external irradiation grid, beryllium block, thermal column and the water reflector in the reactor tank next to the tank wall. As a result of these calculations, the thermal neutron fluxes within the thermal column and at irradiation positions within the thermal column were obtained. Apart from this, the burn up results for the start up core calculated according to the TRITION code were compared with those given by the reactor designer.

  4. Apollo-L2, an advanced fuel tokamak reactor utilizing direct conversion

    International Nuclear Information System (INIS)

    Emmert, G.A.; Kulcinski, G.L.; Blanchard, J.P.; El-Guebaly, L.A.; Khater, H.Y.; Santarius, J.F.; Sawan, M.E.; Sviatoslavsky, I.N.; Wittenberg, L.J.; Witt, R.J.

    1989-01-01

    A scoping study of a tokamak reactor fueled by a D- 3 He plasma is presented. The Apollo D- 3 He tokamak capitalizes on recent advances in high field magnets (20 T) and utilizes rectennas to convert the synchrotron radiation directly to electricity. The low neutron wall loading (0.1 MW/m 2 ) permits a first wall lasting the life of the plant and enables the reactor to be classified as inherently safe. The cost of electricity is less than that from a similar power level DT reactor. 10 refs., 1 fig., 4 tabs

  5. Reactor containment and reactor safety in the United States

    International Nuclear Information System (INIS)

    Kouts, H.

    1986-01-01

    The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.) [pt

  6. Rapid data acquisition from the safety system of the FRJ-2 reactor

    International Nuclear Information System (INIS)

    Inhoven, H.

    1980-06-01

    The central department for research reactors (ZFR) of the Juelich Nuclear Research Centre (KFA) is operating the reactors FRJ-1 (MERLIN) and FRJ-2 (DIDO) since 1962. In 1976, a Siemens 330 computer has been put into operation especially for the processing of data from the DIDO reactor, followed by another computer of the same type for the purpose of processing data from the ZFR department in general. The present report is a result of the work investigating 'Data acquisition and data processing in the FRJ-2' and primarily discusses the complex of 'fast analog and binary signals'. The activities in this field of work have been and still are mainly concerned with general problems encountered in adapting a currently 14-year-old reactor system to a digital computer, namely problems such as data decoupling in the safety system of the reactor, data acquisition using the CAMAC system, data transfer via an 'extended branch', data acquisition software as core-resident programs, temporary storage as common data, interpreting software as peripheral - storage - resident programs. (orig./WB) [de

  7. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

  8. Reactor Physics Programme

    International Nuclear Information System (INIS)

    De Raedt, C.

    2000-01-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

  9. Estimation of power feedback parameters of pulse reactor IBR-2M on transients

    International Nuclear Information System (INIS)

    Pepyolyshev, Yu.N.; Popov, A.K.

    2013-01-01

    Parameters of the IBR-2M reactor power feedback (PFB) on a model of the reactor dynamics by mathematical treatment of two registered transients are estimated. Frequency characteristics and the pulse transient characteristics corresponding to these PFB parameters are calculated. PFB parameters received thus can be considered as their express tentative estimation as real measurements in this case occupy no more than 30 minutes. Total PFB is negative at 1 and 2 MW. At the received estimations of PFB parameters in a self-regulation mode it is possible to consider the stability margins of the IBR-2M reactor satisfactory

  10. Independent CO2 loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Task 2.50.05

    International Nuclear Information System (INIS)

    Stojic, M.; Pavicevic, M.

    1964-01-01

    This report contains the following volumes V and VI of the Project 'Independent CO 2 loop for cooling the samples irradiated in RA reactor vertical experimental channels': Design project of the dosimetry control system in the independent CO 2 loop for cooling the samples irradiated in the RA reactor vertical experimental channels, and Safety report for the Independent CO 2 loop for cooling the samples irradiated in the RA reactor vertical experimental channels [sr

  11. PSA Level 2 activities for RBMK reactors

    International Nuclear Information System (INIS)

    Gubler, R.

    1998-01-01

    Probabilistic safety analyses (PSAs) of the boiling water graphite moderated pressure tube reactors (RBMKs) have been developed only recently and they are limited to Level 1. Activities at the IAEA were first motivated because of the difficulties to characterize core damage for RBMK reactors. Core damage probability is used in documents of the IAEA as a convenient single valued measure, for example for probabilistic safety criteria. The limited number of PSAs that have been completed for the RBMK reactors have shown that several special features of these channel type reactors necessitate revisiting of the characterization of core damage for these reactors. Furthermore, it has become increasingly evident that detailed deterministic analysis of DBAs and beyond design basis accidents reveal considerable insights into RBMK response to various accident conditions. These analyses can also help in better characterizing the outstanding phenomenological uncertainties, improved EOPs and AM strategies, including potential risk-beneficial accident negative backfits. The deterministic efforts should be focused first on elucidating accident progression processes and phenomena, and second on finding, qualifying and implementing procedures to minimize the risk of severe accident states The IAEA PSA procedures were mainly developed in New of vessel type LWRs, and would therefore require extensions to make them directly applicable. to channel type reactors. (author) (author)

  12. Studsvik's R2 reactor - Review of activities

    Energy Technology Data Exchange (ETDEWEB)

    Grounes, Mikael; Tomani, Hans; Graeslund, Christian; Rundquist, Hans; Skoeld, Kurt [Studsvik Nuclear AB, Nykoeping (Sweden)

    1993-07-01

    A general description of the R2 reactor, its associated facilities and its history is given. The facilities and range of work are described for the following types of activities: fuel testing, materials testing, neutron transmutation doping of silicon, activation analysis, radioisotope production and basic research including thermal neutron scattering, nuclear chemistry and neutron capture radiography. (author)

  13. Decommissioning of reactor facilities (2). Required technology

    International Nuclear Information System (INIS)

    Yanagihara, Satoshi

    2014-01-01

    Decommissioning of reactor facilities was planned to perform progressive dismantling, decontamination and radioactive waste disposal with combination of required technology in a safe and economic way. This article outlined required technology for decommissioning as follows: (1) evaluation of kinds and amounts of residual radioactivity of reactor facilities with calculation and measurement, (2) decontamination technology of metal components and concrete structures so as to reduce worker's exposure and production of radioactive wastes during dismantling, (3) dismantling technology of metal components and concrete structures such as plasma arc cutting, band saw cutting and controlled demolition with mostly remote control operation, (3) radioactive waste disposal for volume reduction and reuse, and (4) project management of decommissioning for safe and rational work to secure reduction of worker's exposure and prevent the spreading of contamination. (T. Tanaka)

  14. Reproduction of the PSBR reactor with Exterminator-2; Reproduccion del reactor PSBR con exterminador-2

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar H, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    1983-08-15

    To reproduce the reactor PSBR reported in (1), with the available version of the Exterminator-II in the ININ, they took the dimensions, composition specifications, effective sections of the different compositions (excepting those of the central thimble and of the moderator), the K{sub eff} and the factors of power (FP) for the different burners. Based on the comparison of the K{sub eff} and of the FP obtained with those reported the precision it is determined before in the reproduction of the reactor mentioned. (Author)

  15. Evaluation of the human immunodeficiency virus type 1 and 2 antibodies detection in dried whole blood spots (dbs samples Pesquisa de anticorpos contra o vírus da imunodeficiência humana tipos 1 e 2 em amostras de sangue seco coletadas em papel filtro

    Directory of Open Access Journals (Sweden)

    Andréa Cauduro de Castro

    2008-06-01

    Full Text Available Human Immunodeficiency Vírus Type 1 and 2 antibodies detection was performed in 457 dried whole blood spots samples (S&S 903. Q-Preven HIV 1+2 was the screening test used. The results were compared with the gold standard serum tests by ELISA (Cobas Core e Axsym HIV1/2 gO and imunofluorescence was the definitive confirmatory test. The samples were obtained from the Hospital Nossa Senhora da Conceição in Porto Alegre, RS - Brazil, through whole blood transfer to filter paper card and sent to Caxias do Sul, RS - Brazil where the tests were performed. The dried whole blood spot stability was evaluated with two different panels. The first one was composed of five negative and five positive samples stored at room temperature, 4 ºC, -20 ºC and -70 ºC, while the second was composed of two negative and three positive samples stored at 37 ºC (humidity Foram realizados 457 testes para detectar anticorpos contra o Vírus da Imunodeficiência Humana tipos 1 e 2, em amostras de sangue total seco coletadas em papel filtro (S&S 903, com o teste de triagem Q-Preven HIV 1+2, comparando-se com os resultados dos testes de triagem no soro (Cobas Core e Axsym HIV1/2 gO, sendo a imunofluorescência indireta o teste confirmatório. As amostras foram obtidas no Hospital Conceição em Porto Alegre, pela transferência de sangue total para cartão de papel filtro e encaminhadas para Caxias do Sul para a realização dos testes. Foi analisada a estabilidade da amostra em papel filtro com a utilização de dois painéis: o primeiro com cinco amostras negativas e cinco positivas armazenadas por seis semanas à temperatura ambiente, 4 ºC, -20 ºC e -70 ºC; o segundo com duas negativas e três positivas armazenadas por seis semanas com avaliações semanais a 37 ºC (umidade <50%. Os resultados de todas as amostras testadas foram mantidos. A sensibilidade foi de 100%, a especificidade de 99,6%, o valor preditivo positivo de 99,5% e o valor preditivo negativo de 100

  16. Production of Sn-117m in the BR2 high-flux reactor.

    Science.gov (United States)

    Ponsard, B; Srivastava, S C; Mausner, L F; Russ Knapp, F F; Garland, M A; Mirzadeh, S

    2009-01-01

    The BR2 reactor is a 100MW(th) high-flux 'materials testing reactor', which produces a wide range of radioisotopes for various applications in nuclear medicine and industry. Tin-117m ((117m)Sn), a promising radionuclide for therapeutic applications, and its production have been validated in the BR2 reactor. In contrast to therapeutic beta emitters, (117m)Sn decays via isomeric transition with the emission of monoenergetic conversion electrons which are effective for metastatic bone pain palliation and radiosynovectomy with lesser damage to the bone marrow and the healthy tissues. Furthermore, the emitted gamma photons are ideal for imaging and dosimetry.

  17. Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) are compared

    International Nuclear Information System (INIS)

    Greneche, D.

    2014-01-01

    This article compares the 2 types of light water reactors that are used to produce electricity: the Pressurized Water Reactor (PWR) and the Boiling Water Reactor (BWR). Historically the BWR concept was developed after the PWR concept. Today 80% of light water reactors operating in the world are of PWR-type. This comparison is comprehensive and detailed. First the main technical features are reviewed and compared: reactor architecture, core and fuel design, reactivity control, reactor vessel, cooling systems and reactor containment. Secondly, various aspects concerning reactor operations like reactor control, fuel management, maintenance, inspections, radiation protection, waste generation and reactor reliability are presented and compared for both reactors. As for the issue of safety, it is highlighted that the accidental situations are too different for the 2 reactors to be compared. The main features of reactor safety are explained for both reactors

  18. Proceedings of 2. Yugoslav symposium on reactor physics, Part 1, Herceg Novi (Yugoslavia), 27-29 Sep 1966

    International Nuclear Information System (INIS)

    1966-01-01

    This Volume 1 of the Proceedings of 2. Yugoslav symposium on reactor physics includes nine papers dealing with the following topics: reactor kinetics, reactor noise, neutron detection, methods for calculating neutron flux spatial and time dependence in the reactor cores of both heavy and light water moderated experimental reactors, calculation of reactor lattice parameters, reactor instrumentation, reactor monitoring systems; measuring methods of reactor parameters; reactor experimental facilities

  19. Comparative study between fluidized bed and fixed bed reactors in methane reforming with CO2 and O2 to produce syngas

    International Nuclear Information System (INIS)

    Jing Qiangshan; Lou Hui; Mo Liuye; Zheng Xiaoming

    2006-01-01

    Reforming of methane with carbon dioxide and oxygen was investigated over Ni/MgO-SiO 2 catalysts using fixed bed and fluidized bed reactors. The conversions of CH 4 and CO 2 in a fluidized bed reactor were close to thermodynamic equilibrium. The activity and stability of the catalyst in the fixed bed reactor were lower than that in the fluidized bed reactor due to carbon deposition and nickel sintering. TGA and TEM techniques were used to characterize the spent catalysts. The results showed that a lot of whisker carbon was found on the catalyst in the rear of the fixed bed reactor, and no deposited carbon was observed on the catalysts in the fluidized bed reactor after reaction. It is suggested that this phenomenon is related to a permanent circulation of catalyst particles between the oxygen rich and oxygen free zones. That is, fluidization of the catalysts in the fluidized bed reactor favors inhibiting deposited carbon and thermal uniformity in the reactor

  20. Benchmark testing of Canadol-2.1 for heavy water reactor

    International Nuclear Information System (INIS)

    Liu Ping

    1999-01-01

    The new version evaluated nuclear data library of ENDF-B 6.5 has been released recently. In order to compare the quality of evaluated nuclear data CENDL-2.1 with ENDF-B 6.5, it is necessary to do benchmarks testing for them. In this work, CENDL-2.1 and ENDF-B 6.5 were used to generated the WIMS-69 group library respectively, and benchmarks testing was done for the heavy water reactor, using WIMS5A code. It is obvious that data files of CENDL-2.1 is better than that of old WIMS library for the heavy water reactors calculations, and is in good agreement with those of ENDF-B 6.5

  1. Oxygen suppression in boiling water reactors. Phase 2. Annual report 1981, December 2, 1980-December 31, 1981

    International Nuclear Information System (INIS)

    Burley, E.L.

    1982-07-01

    A hydrogen addition test will be performed in the Dresden-2 reactor of Commonwealth Edison Company during 1982. Up to 2 ppM hydrogen will be added to and dissolved in the reactor feedwater to reverse the radiolysis reaction in the reactor core and suppress oxgen concentration in the primary coolant. At low oxygen levels the propensity of stressed and sensitized 304 stainless steel toward intergranular stress corrosion cracking is greatly reduced. The test will answer outstanding questions and uncertainties in the areas of water chemistry, equipment design and materials performance. Nine special sample facilities will be prepared in the primary coolant, main stream, feedwater/condensate, and offgas systems. Instrumentation will be available to measure hydrogen, oxygen, conductivity, pH, soluble and insoluble corrosion products, and electrochemical potentials. In addition, an autoclave in which confirming constant extension rate tests can be conducted in reactor water will be provided

  2. Adaptive Management Using Remote Sensing and Ecosystem Modeling in Response to Climate Variability and Invasive Aquatic Plants for the California Sacramento-San Joaquin Delta Water Resource

    Science.gov (United States)

    Bubenheim, David; Potter, Christopher; Zhang, Minghua; Madsen, John

    2017-01-01

    The California Sacramento-San Joaquin River Delta is the hub for California's water supply and supports important ecosystem services, agriculture, and communities in Northern to Southern California. Expansion of invasive aquatic plants in the Delta coupled with impacts of changing climate and long-term drought is detrimental to the San Francisco Bay/California Delta complex. NASA Ames Research Center and the USDA-ARS partnered with the State of California to develop science-based, adaptive-management strategies for invasive aquatic plant in the Sacramento-San Joaquin Delta. Specific mapping tools developed utilizing satellite and airborne platforms provide regular assessments of population dynamics on a landscape scale and support both strategic planning and operational decision making for resource managers. San Joaquin and Sacramento River watersheds water quality input to the Delta is modeled using the Soil-Water Assessment Tool (SWAT) and a modified SWAT tool has been customized to account for unique landscape and management of agricultural water supply and drainage within the Delta. Environmental response models for growth of invasive aquatic weeds are being parameterized and coupled with spatial distribution/biomass density mapping and water quality to study ecosystem response to climate and aquatic plant management practices. On the water validation and operational utilization of these tools by management agencies and how they are improving decision making, management effectiveness and efficiency will be discussed. The project combines science, operations, and economics related to integrated management scenarios for aquatic weeds to help land and water resource managers make science-informed decisions regarding management and outcomes.

  3. Adaptive Management Using Remote Sensing and Ecosystem Modeling in Response to Climate Variability and Invasive Aquatic Plants for the California Sacramento-San Joaquin Delta Water Resource

    Science.gov (United States)

    Bubenheim, D.; Potter, C. S.; Zhang, M.; Madsen, J.

    2017-12-01

    The California Sacramento-San Joaquin River Delta is the hub for California's water supply and supports important ecosystem services, agriculture, and communities in Northern and Southern California. Expansion of invasive aquatic plants in the Delta coupled with impacts of changing climate and long-term drought is detrimental to the San Francisco Bay/California Delta complex. NASA Ames Research Center and the USDA-ARS partnered with the State of California to develop science-based, adaptive-management strategies for invasive aquatic plant management in the California Sacramento-San Joaquin Delta. Specific mapping tools developed utilizing satellite and airborne platforms provide regular assessments of population dynamics on a landscape scale and support both strategic planning and operational decision making for resource managers. San Joaquin and Sacramento River watersheds water quality input to the Delta is modeled using the Soil-Water Assessment Tool (SWAT) and a modified SWAT tool has been customized to account for unique landscape and management of agricultural water supply and drainage within the Delta. Environmental response models for growth of invasive aquatic weeds are being parameterized and coupled with spatial distribution/biomass density mapping and water quality to study ecosystem response to climate and aquatic plant management practices. On the water validation and operational utilization of these tools by management agencies and how they improve decision making, management effectiveness and efficiency will be discussed. The project combines science, operations, and economics related to integrated management scenarios for aquatic weeds to help land and water resource managers make science-informed decisions regarding management and outcomes.

  4. Characterization of fuel distributions in the Three-Mile Island Unit 2 (TMI-2) reactor system by neutron and gamma-ray dosimetry

    International Nuclear Information System (INIS)

    Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McNeece, J.P.; Kaiser, B.J.; McElroy, W.N.

    1984-04-01

    The resolution of technical issues generated by the accident at Three-Mile Island Unit 2 (TMI-2) will inevitably be of long range benefit. Determination of the fuel debris dispersal in the TMI-2 reactor system represents a major technical issue. In reactor recovery operations, such as for the safe handling and final disposal of TMI-2 waste, quantitative fuel assessments are being conducted throughout the reactor core and primary coolant system

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

    International Nuclear Information System (INIS)

    Bissani, M; O'Kelly, D S

    2006-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Bissani, M; O' Kelly, D S

    2006-05-08

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

  7. analysis and implementation of reactor protection system circuits - case study Egypt's 2 nd research reactor-

    International Nuclear Information System (INIS)

    Elnokity, O.E.M.

    2006-01-01

    this work presents a way to design and implement the trip unit of a reactor protection system (RPS) using a field programmable gate arrays (FPGA). instead of the traditional embedded microprocessor based interface design method, a proposed tailor made FPGA based circuit is built to substitute the trip unit (TU), which is used in Egypt's 2 nd research reactor ETRR-2. the existing embedded system is built around the STD32 field computer bus which is used in industrial and process control applications. it is modular, rugged, reliable, and easy-to-use and is able to support a large mix of I/O cards and to easily change its configuration in the future. therefore, the same bus is still used in the proposed design. the state machine of this bus is designed based around its timing diagrams and implemented in VHDL to interface the designed TU circuit

  8. Inter-population differences in salinity tolerance and osmoregulation of juvenile wild and hatchery-born Sacramento splittail

    Science.gov (United States)

    Verhille, Christine E.; Dabruzzi, Theresa F.; Cocherell, Dennis E.; Mahardja, Brian; Feyrer, Frederick V.; Foin, Theodore C.; Baerwald, Melinda R.; Fangue, Nann A.

    2016-01-01

    The Sacramento splittail (Pogonichthys macrolepidotus) is a minnow endemic to the highly modified San Francisco Estuary of California, USA and its associated rivers and tributaries. This species is composed of two genetically distinct populations, which, according to field observations and otolith strontium signatures, show largely allopatric distribution patterns as recently hatched juveniles. Juvenile Central Valley splittail are found primarily in the nearly fresh waters of the Sacramento and San Joaquin rivers and their tributaries, whereas San Pablo juveniles are found in the typically higher-salinity waters (i.e. up to 10‰) of the Napa and Petaluma Rivers. As the large salinity differences between young-of-year habitats may indicate population-specific differences in salinity tolerance, we hypothesized that juvenile San Pablo and Central Valley splittail populations differ in their response to salinity. In hatchery-born and wild-caught juvenile San Pablo splittail, we found upper salinity tolerances, where mortalities occurred within 336 h of exposure to 16‰ or higher, which was higher than the upper salinity tolerance of 14‰ for wild-caught juvenile Central Valley splittail. This, in conjunction with slower recovery of plasma osmolality, but not ion levels, muscle moisture or gill Na+,K+-ATPase activity, in Central Valley relative to San Pablo splittail during osmoregulatory disturbance provides some support for our hypothesis of inter-population variation in salinity tolerance and osmoregulation. The modestly improved salinity tolerance of San Pablo splittail is consistent with its use of higher-salinity habitats. Although confirmation of the putative adaptive difference through further studies is recommended, this may highlight the need for population-specific management considerations.

  9. General outline of the operation and utilization of the BR2 reactor

    International Nuclear Information System (INIS)

    Baugnet, J.M.; Leonard, F.; Gandolfo, J.M.; Lenders, H.

    1978-01-01

    The BR2 reactor is a high-flux material testing reactor of the thermal heterogeneous type. The fuel is 93% 235 U enriched uranium in the form of plates clad in aluminium. The moderator consists of beryllium and light water, the water being pressurized (12.5kg/cm 2 )and acting also as coolant. The pressure vessel is of aluminium, and is placed in a pool of demineralized water. One should stress the following main features of the design: the experimental channels are skew, the tube bundle presenting the form of a hyperboloid of revolution (see figure 1)-this gives easy access at the top and bottom reactor covers allowing complex instrumented devices, while maintaining a very high neutron flux at the core; great flexibilty of utilization, due to the fact that it is possible to adapt the core configuration to the experimental loading as the fissile charge can be centred on different experimental channels; although BR2 is a thermal reactor, it is possible to achieve neutron spectra very similar to those obtained in a fast reactor, either by the use of absorbing screens or by the use of fissile material within the experimental device; five 200mm diameter channels are available for loading large experimental irradiation devices, as in-pile sodium, gas or water loops. (author)

  10. Benchmark testing of CENDL-2 for U-fuel thermal reactors

    International Nuclear Information System (INIS)

    Zhang Baocheng; Liu Guisheng; Liu Ping

    1995-01-01

    Based on CENDL-2, NJOY-WIMS code system was used to generate 69-group constants, and do benchmark testing for TRX-1,2; BAPL-UO-2-1,2,3; ZEEP-1,2,3. All the results proved that CENDL-2 is reliable for thermal reactor calculations. (3 tabs.)

  11. Shadow corrosion testing in the INCA facility in the Studsvik R2 reactor

    International Nuclear Information System (INIS)

    Nystrand, A.C.; Lassing, A.

    1999-01-01

    Shadow corrosion is a phenomenon which occurs when zirconium alloys are in contact with or in proximity to other metallic objects in a boiling water reactor environment (BWR, RBMK, SGHWR etc.). An enhanced corrosion occurs on the zirconium alloy with the appearance of a 'shadow' of the metallic object. The magnitude of the shadow corrosion can be significant, and is potentially limiting for the lifetime of certain zirconium alloy components in BWRs and other reactors with a similar water chemistry. In order to evaluate the suitability of the In-Core Autoclave (INCA) in the Studsvik R2 materials testing reactor as an experimental facility for studying shadow corrosion, a demonstration test has been performed. A number of test specimens consisting of Zircaloy-2 tubing in contact with Inconel were exposed in an oxidising water chemistry. Some of the specimens were placed within the reactor core and some above the core. The conclusion of this experiment after post irradiation examination is that it is possible to use the INCA facility in the Studsvik R2 reactor to develop a significant level of shadow corrosion after only 800 hours of irradiation. (author)

  12. The 5th surveillance testing for Kori unit 2 reactor vessel materials

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Kee Ok; Kim, Byoung Chul; Lee, Sam Lai; Choi, Kwon Jae; Gong, Un Sik; Chang, Jong Hwa; Joo, Yong Sun; Ahn, Sang Bok; Hong, Joon Hwa [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2001-03-01

    Surveillance testing for reactor vessel materials is performed in order to evaluate the irradiation embrittlement due to neutrons during operation and set the condition of safe operation of nuclear reactor. The 5th surveillance testing was performed completely by Korea Atomic Energy Research Institute at Taejeon after the capsule was transported from Kori site including its removal from reactor. Fast neutron fluences for capsules were calculated and various testing including mechanical and chemistry analysis were performed in order to evaluate the integrity of Kori unit 2 reactor vessel during the operation until life time. The evaluation results are as follows; Fast neutron fluences for capsules V, R, P, T and N are 2.837E+18, 1.105E+19, 2.110E+19, 3.705E+19 and 4.831E+19n/cm{sup 2}, respectively. The bias factor, the ratio of measurement/calculation, was 0.918 for the 1st through 5th testing and the calculational uncertainty, 11.6% satisfied the requirement of USNRC Reg.Guide DG-1053, 20%. The best estimated neutron fluence for reactor vessel inside surface was 1.898E+19n/cm{sup 2} based on the end of 15th fuel cycle and it was predicted that the fluences of vessel inside surface at 32, 40, 48 and 56EFPY would reach 4.203E+19, 5.232E+19, 6.262E+19 and 7.291E+19n/cm{sup 2} based on the current calculation. The result through this analysis for Kori unit 2 showed that there would be no problem for the pressurized thermal shock(PTS) during the operation until design life. 49 refs., 35 figs., 48 tabs. (Author)

  13. Digital, remote control system for a 2-MW research reactor

    International Nuclear Information System (INIS)

    Battle, R.E.; Corbett, G.K.

    1988-01-01

    A fault-tolerant programmable logic controller (PLC) and operator workstations have been programmed to replace the hard-wired relay control system in the 2-MW Bulk Shielding Reactor (BSR) at Oak Ridge National Laboratory. In addition to the PLC and remote and local operator workstations, auxiliary systems for remote operation include a video system, an intercom system, and a fiber optic communication system. The remote control station, located at the High Flux Isotope Reactor 2.5 km from the BSR, has the capability of rector startup and power control. The system was designed with reliability and fail-safe features as important considerations. 4 refs., 3 figs

  14. A nodal Grean's function method of reactor core fuel management code, NGCFM2D

    International Nuclear Information System (INIS)

    Li Dongsheng; Yao Dong.

    1987-01-01

    This paper presents the mathematical model and program structure of the nodal Green's function method of reactor core fuel management code, NGCFM2D. Computing results of some reactor cores by NGCFM2D are analysed and compared with other codes

  15. RHTF 2, a 1200 MWe high temperature reactor

    International Nuclear Information System (INIS)

    Brisbois, Jacques

    1978-01-01

    After having adapted to French conditions the 1160 MWe G.A.C. reactor, Commissariat a l'Energie Atomique and French Industry have decided to design an High Temperature Reactor 1200 MWe based on the G.A.C. technology and taking into account the point of view of Electricite de France and the experience of C.E.A. and industry on the gas cooled reactor technology. The main objective of this work is to produce a reactor design having a low technical risk, good operability, with an emphasis on the safety aspects easing the licensing problems

  16. Turkey's regulatory plans for high enriched to low enriched conversion of TR-2 reactor core

    International Nuclear Information System (INIS)

    Guelol Oezdere, Oya

    2003-01-01

    Turkey is a developing country and has three nuclear facilities two of which are research reactors and one pilot fuel production plant. One of the two research reactors is TR-2 which is located in Cekmece site in Istanbul. TR-2 Reactor's core is composed of both high enriched and low enriched fuel and from high enriched to low enriched core conversion project will take place in year 2005. This paper presents the plans for drafting regulations on the safety analysis report updates for high enriched to low enriched core conversion of TR-2 reactor, the present regulatory structure of Turkey and licensing activities of nuclear facilities. (author)

  17. Agricultural peatland restoration: effects of land-use change on greenhouse gas (CO2 and CH4) fluxes in the Sacramento-San Joaquin Delta.

    Science.gov (United States)

    Knox, Sara Helen; Sturtevant, Cove; Matthes, Jaclyn Hatala; Koteen, Laurie; Verfaillie, Joseph; Baldocchi, Dennis

    2015-02-01

    Agricultural drainage of organic soils has resulted in vast soil subsidence and contributed to increased atmospheric carbon dioxide (CO2) concentrations. The Sacramento-San Joaquin Delta in California was drained over a century ago for agriculture and human settlement and has since experienced subsidence rates that are among the highest in the world. It is recognized that drained agriculture in the Delta is unsustainable in the long-term, and to help reverse subsidence and capture carbon (C) there is an interest in restoring drained agricultural land-use types to flooded conditions. However, flooding may increase methane (CH4) emissions. We conducted a full year of simultaneous eddy covariance measurements at two conventional drained agricultural peatlands (a pasture and a corn field) and three flooded land-use types (a rice paddy and two restored wetlands) to assess the impact of drained to flooded land-use change on CO2 and CH4 fluxes in the Delta. We found that the drained sites were net C and greenhouse gas (GHG) sources, releasing up to 341 g C m(-2) yr(-1) as CO2 and 11.4 g C m(-2) yr(-1) as CH4. Conversely, the restored wetlands were net sinks of atmospheric CO2, sequestering up to 397 g C m(-2) yr(-1). However, they were large sources of CH4, with emissions ranging from 39 to 53 g C m(-2) yr(-1). In terms of the full GHG budget, the restored wetlands could be either GHG sources or sinks. Although the rice paddy was a small atmospheric CO2 sink, when considering harvest and CH4 emissions, it acted as both a C and GHG source. Annual photosynthesis was similar between sites, but flooding at the restored sites inhibited ecosystem respiration, making them net CO2 sinks. This study suggests that converting drained agricultural peat soils to flooded land-use types can help reduce or reverse soil subsidence and reduce GHG emissions. © 2014 John Wiley & Sons Ltd.

  18. Techno-economic assessment of membrane assisted fluidized bed reactors for pure H_2 production with CO_2 capture

    International Nuclear Information System (INIS)

    Spallina, V.; Pandolfo, D.; Battistella, A.; Romano, M.C.; Van Sint Annaland, M.; Gallucci, F.

    2016-01-01

    Highlights: • Membrane reactors improve the overall efficiency of H_2 production up to 20%. • Respect to conventional reforming, the H_2 yield increases from 12% to 20%. • The COH is reduced of at least 220% using membrane reactors. • FBMR capture 72% of CO_2 with a specific cost of 8 eur/tonn_C_O_2_. • MA-CLR can reach 90% of CO_2 avoided with same cost of FTR. - Abstract: This paper addresses the techno-economic assessment of two membrane-based technologies for H_2 production from natural gas, fully integrated with CO_2 capture. In the first configuration, a fluidized bed membrane reactor (FBMR) is integrated in the H_2 plant: the natural gas reacts with steam in the catalytic bed and H_2 is simultaneously separated using Pd-based membranes, and the heat of reaction is provided to the system by feeding air as reactive sweep gas in part of the membranes and by burning part of the permeated H_2 (in order to avoid CO_2 emissions for heat supply). In the second system, named membrane assisted chemical looping reforming (MA-CLR), natural gas is converted in the fuel rector by reaction with steam and an oxygen carrier (chemical looping reforming), and the produced H_2 permeates through the membranes. The oxygen carrier is re-oxidized in a separate air reactor with air, which also provides the heat required for the endothermic reactions in the fuel reactor. The plants are optimized by varying the operating conditions of the reactors such as temperature, pressures (both at feed and permeate side), steam-to-carbon ratio and the heat recovery configuration. The plant design is carried out using Aspen Simulation, while the novel reactor concepts have been designed and their performance have been studied with a dedicated phenomenological model in Matlab. Both configurations have been designed and compared with reference technologies for H_2 production based on conventional fired tubular reforming (FTR) with and without CO_2 capture. The results of the analysis show

  19. Reactor building integrity testing: A novel approach at Gentilly 2 - principles and methodology

    International Nuclear Information System (INIS)

    Collins, N.; Lafreniere, P.

    1991-01-01

    In 1987, Hydro-Quebec embarked on an ambitious development program to provide the Gentilly 2 nuclear power station with an effective, yet practical reactor building Integrity Test. The Gentilly 2 Integrity Test employs an innovative approach based on the reference volume concept. It is identified as the Temperature Compensation Method (TCM) System. This configuration has been demonstrated at both high and low test pressure and has achieved extraordinary precision in the leak rate measurement. The Gentilly 2 design allows the Integrity Test to be performed at a nominal 3 kPa(g) test pressure during an (11) hour period with the reactor at full power. The reactor building Pressure Test by comparison, is typically performed at high pressure 124 kPa(g)) in a 7 day window during an annual outage. The Integrity Test was developed with the goal of demonstrating containment availability. Specifically it was purported to detect a leak or hole in the 'bottled-up' reactor building greater in magnitude than an equivalent pipe of 25 mm diameter. However it is considered feasible that the high precision of the Gentilly 2 TCM System Integrity Test and a stable reactor building leak characteristic will constitute sufficient grounds for the reduction of the Pressure Test frequency. It is noted that only the TCM System has, to this date, allowed a relevant determination of the reactor building leak rate at a nominal test pressure of 3 kPa(g). Classical method tests at low pressure have lead to inconclusive results due to the high lack of precision

  20. Changes in Rice Pesticide Use and Surface Water Concentrations in the Sacramento River Watershed, California

    Science.gov (United States)

    Orlando, James L.; Kuivila, Kathryn

    2004-01-01

    Pesticides applied to rice fields in California are transported into the Sacramento River watershed by the release of rice field water. Despite monitoring and mitigation programs, concentrations of two rice pesticides, molinate and thiobencarb, continue to exceed the surface-water concentration performance goals established by the Central Valley Regional Water Quality Control Board. There have been major changes in pesticide use over the past decade, and the total amount of pesticides applied remains high. Molinate use has declined by nearly half, while thiobencarb use has more than doubled; carbofuran has been eliminated and partially replaced by the pyrethroid pesticide lambda-cyhalothrin. A study was conducted in 2002 and 2003 by the U.S. Geological Survey to determine if the changes in pesticide use on rice resulted in corresponding changes in pesticide concentrations in surface waters. During the rice growing season (May-July), water samples, collected weekly at three sites in 2002 and two sites in 2003, were analyzed for pesticides using both solid-phase and liquid-liquid extraction in combination with gas chromatography/mass spectrometry. Analytes included lambda-cyhalothrin, molinate, thiobencarb, and two degradation products of molinate: 2-keto-molinate and 4-keto-molinate. Molinate, thiobencarb, and 4-keto-molinate were detected in all samples, 2-keto-molinate was detected in less than half of the samples, and lambda-cyhalothrin was not detected in any samples. At two of the sites sampled in 2002 (Colusa Basin Drain 1 and Sacramento Slough), concentrations of molinate were similar, but thiobencarb concentrations differed by a factor of five. Although concentrations cannot be estimated directly from application amounts in different watersheds, the ratio of molinate to thiobencarb concentrations can be compared with the ratio of molinate to thiobencarb use in the basins. The higher concentration ratio in the Sacramento Slough Basin, compared with the ratio

  1. Maximum credible accident analysis for TR-2 reactor conceptual design

    International Nuclear Information System (INIS)

    Manopulo, E.

    1981-01-01

    A new reactor, TR-2, of 5 MW, designed in cooperation with CEN/GRENOBLE is under construction in the open pool of TR-1 reactor of 1 MW set up by AMF atomics at the Cekmece Nuclear Research and Training Center. In this report the fission product inventory and doses released after the maximum credible accident have been studied. The diffusion of the gaseous fission products to the environment and the potential radiation risks to the population have been evaluated

  2. UO{sub 2} and PuO{sub 2} utilization in high temperature engineering test reactor with helium coolant

    Energy Technology Data Exchange (ETDEWEB)

    Waris, Abdul, E-mail: awaris@fi.itb.ac.id; Novitrian,; Pramuditya, Syeilendra; Su’ud, Zaki [Nuclear Physics and Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung (Indonesia); Aji, Indarta K. [Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung (Indonesia)

    2016-03-11

    High temperature engineering test reactor (HTTR) is one of high temperature gas cooled reactor (HTGR) types which has been developed by Japanese Atomic Energy Research Institute (JAERI). The HTTR is a graphite moderator, helium gas coolant, 30 MW thermal output and 950 °C outlet coolant temperature for high temperature test operation. Original HTTR uses UO{sub 2} fuel. In this study, we have evaluated the use of UO{sub 2} and PuO{sub 2} in form of mixed oxide (MOX) fuel in HTTR. The reactor cell calculation was performed by using SRAC 2002 code, with nuclear data library was derived from JENDL3.2. The result shows that HTTR can obtain its criticality condition if the enrichment of {sup 235}U in loaded fuel is 18.0% or above.

  3. The Chernobyl reactor accident. Pt. 1 and 2

    International Nuclear Information System (INIS)

    1986-06-01

    The report first summarizes the available information on the various incidents of the whole accident scenario, and combines the information to present a first general outline and a basis for appraisal. The most significant incidents reported, namely power excursion, core meltdown, and fire, are discussed with a view to the reactor design and safety of reactors installed in the FRG. The main differences and advantages of German reactor designs are shown, as e.g.: Power excursions are mastered by inherent physical conditions; far better redundancy of engineered safety systems; enclosure of the complete reactor cooling system in a pressure-retaining steel containment; reactor buildings being made of reinforced concrete. The second part of the report deals with the radiological effects to be expected for our country. Data are given on the varying radiological exposure of the different regions. The fate and uptake of radioactivity in the human body are discussed. The conclusion drawn from the data presented is that the individual exposure due to the reactor accident will remain within the variations and limits of natural radioactivity and effects. (orig./HP) [de

  4. Synthesis of the IRSN report related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor. Referral of the Permanent Group of Experts for nuclear reactors (GPR), examination of probabilistic level-2 safety studies (EPS 2) and severe accidents (AG) of the Flamanville reactor nr 3. Opinion related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor (FA3). Electronuclear reactors - EDF - Flamanville 3 EPR reactor. Severe accidents and probabilistic level 2 studies

    International Nuclear Information System (INIS)

    2015-01-01

    This document gathers several documents. The first one recalls the main arrangements implemented on the FA3 EPR reactor regarding accidents with core fusion, reports the analysis made by the IRSN about the sizing of these arrangements to reach a controlled status of the installation after a severe accident, regarding the probabilistic level-2 safety assessment, regarding the radiological impact of a severe accident on the population and on the environment, regarding those aimed at facing a total and long duration loss of electric power sources and cold sources, and about the situation of the reactor with respect to WENRA positions on severe accidents for new reactors. The second document is a letter sent by the ASN to the Permanent Group of Experts for nuclear reactors (GPR) to address probabilistic level-2 safety studies (EPS2) and severe accidents for the Flamanville 3 reactor. The third one reports the opinion of the GPR on these both issues and proposes a set of recommendations. The next document is a letter sent by the ASN to the Flamanville 3 project manager at EDF which recalls the related objectives, the ASN opinion on the implemented arrangements for severe accidents (de-pressurization of the primary circuit, management of hydrogen-related risks, corium recovery and cooling outside the vessel, limitation of vapour explosion risks outside the vessel, heat evacuation system, containment enclosure, management of the risk of a return to criticality), to face a total and long duration loss of electricity sources and cold sources, and other aspects addressed in the IRSN analysis. Requests and remarks formulated by the ASN are provided in an appendix to this last document

  5. Irradiated graphite studies prior to decommissioning of G1, G2 and G3 reactors

    International Nuclear Information System (INIS)

    Bonal, J.P.; Vistoli, J.Ph.; Combes, C.

    2005-01-01

    G1 (46 MW th ), G2 (250 MW th ) and G3 (250 MW th ) are the first French plutonium production reactors owned by CEA (Commissariat a l'Energie Atomique). They started to be operated in 1956 (G1), 1959 (G2) and 1960 (G3); their final shutdown occurred in 1968, 1980 and 1984 respectively. Each reactor used about 1200 tons of graphite as moderator, moreover in G2 and G3, a 95 tons graphite wall is used to shield the rear side concrete from neutron irradiation. G1 is an air cooled reactor operated at a graphite temperature ranging from 30 C to 230 C; G2 and G3 are CO 2 cooled reactors and during operation the graphite temperature is higher (140 C to 400 C). These reactors are now partly decommissioned, but the graphite stacks are still inside the reactors. The graphite core radioactivity has decreased enough so that a full decommissioning stage may be considered. Conceming this decommissioning, the studies reported here are: (i) stored energy in graphite, (ii) graphite radioactivity measurements, (iii) leaching of radionuclide ( 14 C, 36 Cl, 63 Ni, 60 Co, 3 H) from graphite, (iv) chlorine diffusion through graphite. (authors)

  6. Historic, Recent, and Future Subsidence, Sacramento-San Joaquin Delta, California, USA

    Directory of Open Access Journals (Sweden)

    Steven J Deverel

    2010-08-01

    Full Text Available To estimate and understand recent subsidence, we collected elevation and soils data on Bacon and Sherman islands in 2006 at locations of previous elevation measurements. Measured subsidence rates on Sherman Island from 1988 to 2006 averaged 1.23 cm/year (0.5 in/yr and ranged from 0.7 to 1.7 cm/year (0.3 to 0.7 in/year. Subsidence rates on Bacon Island from 1978 to 2006 averaged 2.2 cm/year (0.9 in/yr and ranged from 1.5 to 3.7 cm/year (0.6 to 1.5 in/yr. Changing land-management practices and decreasing soil organic matter content have resulted in decreasing subsidence rates. On Sherman Island, rates from 1988 to 2006 were about 35% of 1910 to 1988 rates. For Bacon Island, rates from 1978 to 2006 were about 40% less than the 1926-1958 rates. To help understand causes and estimate future subsidence, we developed a subsidence model, SUBCALC, that simulates oxidation and carbon losses, consolidation, wind erosion, and burning and changing soil organic matter content. SUBCALC results agreed well with measured land-surface elevation changes. We predicted elevation decreases from 2007 to 2050 will range from a few centimeters to over 1.3 m (4.3 ft. The largest elevation declines will occur in the central Sacramento-San Joaquin Delta. From 2007 to 2050, the most probable estimated increase in volume below sea level is 349,956,000 million cubic meters (281,300 acre-feet. Consequences of this continuing subsidence include increased drainage loads of water quality constituents of concern, seepage onto islands, and decreased arability.

  7. Reactor core for LMFBR type reactors

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Azekura, Kazuo; Kurihara, Kunitoshi; Bando, Masaru; Watari, Yoshio.

    1987-01-01

    Purpose: To reduce the power distribution fluctuations and obtain flat and stable power distribution throughout the operation period in an LMFBR type reactor. Constitution: In the inner reactor core region and the outer reactor core region surrounding the same, the thickness of the inner region is made smaller than the axial height of the reactor core region and the radial width thereof is made smaller than that of the reactor core region and the volume thereof is made to 30 - 50 % for the reactor core region. Further, the amount of the fuel material per unit volume in the inner region is made to 70 - 90 % of that in the outer region. The difference in the neutron infinite multiplication factor between the inner region and the outer region is substantially constant irrespective of the burnup degree and the power distribution fluctuation can be reduced to about 2/3, by which the effect of thermal striping to the reactor core upper mechanisms can be moderated. Further, the maximum linear power during operation can be reduced by 3 %, by which the thermal margin in the reactor core is increased and the reactor core fuels can be saved by 3 %. (Kamimura, M.)

  8. Striped bass (Morone saxatilis) monitoring techniques in the Sacramento--San Joaquin Estuary

    International Nuclear Information System (INIS)

    Stevens, D.E.

    1977-01-01

    Various methods have been used to monitor the striped bass population in the Sacramento--San Joaquin Estuary. Sampling in the spring with towed plankton nets has provided an adequate description of spawning time and area, but this sampling has not adequately measured egg standing crops and larva and post-larva mortality rates. Tow-net sampling effectively measures the abundance of young in midsummer. A midwater-trawl survey is satisfactory for measuring the abundance of young in the fall but not in the winter. Techniques have not been fully evaluated for monitoring one-year-old bass. Catch-per-unit-effort data from sportfishing party boats were useful for monitoring two-year-olds, until a change in angling regulations increased recruitment age. The Petersen method and indices developed from party-boat catches are the best methods for monitoring bass that are three years old and older. Long-term trends in catch can be monitored through postcard surveys and party-boat catches

  9. Atmospheric transport of pesticides in the Sacramento, California, metropolitan area, 1996-1997

    Science.gov (United States)

    Majewski, Michael S.; Baston, David S.

    2002-01-01

    Weekly composite, bulk air was sampled with respect to wind speed and direction from January 1996 through December 1997 in one urban and two agricultural locations in Sacramento County, California. The sampling sites were located along a north-south transect, the dominant directions of the prevailing winds. The samples were analyzed for a variety of current-use pesticides, including dormant orchard spray insecticides and rice herbicides. A variety of pesticides were detected throughout the year, predominantly chlorpyrifos, diazinon, and trifluralin. The data obtained during the winter and spring suggest that some pesticides used in agricultural areas become airborne and may be transported into the urban area. Confirmation of this drift is difficult, however, because these three predominant pesticides, as well as other detected pesticides, also are heavily used in the urban environment. The spring data clearly show that molinate and thiobencarb, two herbicides used only in rice production, do drift into the urban environment.

  10. A Conceptual Study on a Supercritical CO_2-cooled Micro Modular Reactor

    International Nuclear Information System (INIS)

    Yu, Hwanyeal; Hartanto, Donny; Kim, Yonghee

    2014-01-01

    A Micro Modular Reactor (MMR) using Supercritical-CO_2 (S-CO_2) as coolant has been investigated from the neutronics perspective. The MMR is designed to be transportable so it can reach the remote areas. The thermal power of the reactor is 36.2 M Wth. The size of the active core is limited to 1.2 m length and 93.16 cm width. The size of whole core is 2.8 m length and 166.9 cm width. The reactor lifetime design target is 20 years. To maximize the fuel volume fraction in the core, high density uranium nitride UN"1"5 was used. The PbO/MgO reflector was also utilized to improve the neutron economy. The S-CO_2 is chosen as the coolant because it offers a higher thermal efficiency. In this study, neutronics calculations and depletion using McCARD Monte Carlo code has been done to determine the lifetime and behavior of the core. Several important safety parameters such as Control Rod worth, Doppler reactivity coefficients and coolant void reactivity coefficient have also been analyzed. (author)

  11. Comparison of the N Reactor and Ignalina Unit No. 2 Level 1 Probabilistic Safety Assessments

    International Nuclear Information System (INIS)

    Coles, G.A.; McKay, S.L.

    1995-06-01

    A multilateral team recently completed a full-scope Level 1 Probabilistic Safety Assessment (PSA) on the Ignalina Unit No. 2 reactor plant in Lithuania. This allows comparison of results to those of the PSA for the U.S. Department of Energy's (DOE) N Reactor. The N Reactor, although unique as a Western design, has similarities to Eastern European and Soviet graphite block reactors

  12. Data of evolutionary structure change: 1ONAD-2D3PA [Confc[Archive

    Lifescience Database Archive (English)

    Full Text Available 1ONAD-2D3PA 1ONA 2D3P D A ADTIVAVELDTYPNTDIGDPSYPHIGIDIKSVRSKKTAK...WNMQNGKVGTAHIIYNSVDKRLSAVVSYPNADSATVSYDVDLDNVLPEWVRVGLSASTGLYKETNTILSWSFTSKLKT------NALHFMFNQFSKDQKDLILQGDAT...ONA D 1ONAD LTRVSSNGSPQ <seco

  13. CHAP-2 heat-transfer analysis of the Fort St. Vrain reactor core

    International Nuclear Information System (INIS)

    Kotas, J.F.; Stroh, K.R.

    1983-01-01

    The Los Alamos National Laboratory is developing the Composite High-Temperature Gas-Cooled Reactor Analysis Program (CHAP) to provide advanced best-estimate predictions of postulated accidents in gas-cooled reactor plants. The CHAP-2 reactor-core model uses the finite-element method to initialize a two-dimensional temperature map of the Fort St. Vrain (FSV) core and its top and bottom reflectors. The code generates a finite-element mesh, initializes noding and boundary conditions, and solves the nonlinear Laplace heat equation using temperature-dependent thermal conductivities, variable coolant-channel-convection heat-transfer coefficients, and specified internal fuel and moderator heat-generation rates. This paper discusses this method and analyzes an FSV reactor-core accident that simulates a control-rod withdrawal at full power

  14. Development of Zr-2.5Nb pressure tubes for Advanced CANDU Reactor

    International Nuclear Information System (INIS)

    Bickel, G.A.; Griffiths, M.; Douchant, A.; Douglas, S.; Woo, O.T.; Buyers, A.

    2010-01-01

    In an Advanced CANDU Reactor (ACR), pressure tubes of cold-worked Zr-2.5Nb materials will be used in the reactor core to contain the fuel bundles and the light water coolant. They will be subjected to higher temperature, pressure and flux than that in a CANDU reactor. In order to ensure that these tubes will perform acceptably over their 30-year design life in such an environment, a manufacturing process has been developed to produce 6.5 mm thick ACR pressure tubes with optimized chemical composition, improved mechanical properties and in-reactor behaviour. The test and examination results show that, when compared with current in-service pressure tubes, the mechanical properties of ACR pressure tubes are significantly improved. Based on previous experience with CANDU reactor pressure tubes an assessment of the grain structure and texture indicates that the in-reactor creep deformation will be improved also. Analysis of the distribution of texture parameters from a trial batch of 26 tubes shows that the variability is reduced relative to tubes fabricated in the past. This reduction in variability together with a shift to a coarser grain structure will result in a reduction in diametral creep design limits and thus a longer economic life for the fuel channels of the advanced CANDU reactor. (author)

  15. Preliminary Design of S-CO2 Brayton Cycle for KAIST Micro Modular Reactor

    International Nuclear Information System (INIS)

    Kim, Seong Gu; Kim, Min Gil; Bae, Seong Jun; Lee, Jeong Ik

    2013-01-01

    This paper suggests a complete modular reactor with an innovative concept of reactor cooling by using a supercritical carbon dioxide directly. Authors propose the supercritical CO 2 Brayton cycle (S-CO 2 cycle) as a power conversion system to achieve small volume of power conversion unit (PCU) and to contain the core and PCU in one vessel for the full modularization. This study suggests a conceptual design of small modular reactor including PCU which is named as KAIST Micro Modular Reactor (MMR). As a part of ongoing research of conceptual design of KAIST MMR, preliminary design of power generation cycle was performed in this study. Since the targets of MMR are full modularization of a reactor system with S-CO 2 coolant, authors selected a simple recuperated S-CO 2 Brayton cycle as a power conversion system for KAIST MMR. The size of components of the S-CO 2 cycle is much smaller than existing helium Brayton cycle and steam Rankine cycle, and whole power conversion system can be contained with core and safety system in one containment vessel. From the investigation of the power conversion cycle, recompressing recuperated cycle showed higher efficiency than the simple recuperated cycle. However the volume of heat exchanger for recompressing cycle is too large so more space will be occupied by heat exchanger in the recompressing cycle than the simple recuperated cycle. Thus, authors consider that the simple recuperated cycle is more suitable for MMR. More research for the KAIST MMR will be followed in the future and detailed information of reactor core and safety system will be developed down the road. More refined cycle layout and design of turbomachinery and heat exchanger will be performed in the future study

  16. Severe accident analysis for level 2 PSA of SMART reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jin Yong; Lee, Jeong Hun; Kim, Jong Uk; Yoo, Tae Geun; Chung, Soon Il; Kim, Min Gi [FNC Technology Co., Seoul (Korea, Republic of)

    2010-12-15

    The objectives of this study are to produce data for level 2 PSA and evaluation results of severe accident by analyzing severe accident sequence of transient events, producing fault tree of containment systems and evaluating direct containment heating of the SMART. In this project, severe accident analysis results were produced for general transient, loss of feedwater, station blackout, and steam line break events, and based on the results, design safety of SMART was verified. Also, direct containment heating phenomenon of the SMART was evaluated using TCE methodology. For level 2 PSA, fault tree of the containment isolation system, reactor cavity flooding system, plant chilled water system, and reactor containment building HVAC system was produced and analyzed

  17. Recent advances in the utilization and the irradiation technology of the refurbished BR2 reactor

    International Nuclear Information System (INIS)

    Dekeyser, J.; Benoit, P.; Decloedt, C.; Pouleur, Y.; Verwimp, A.; Weber, M.; Vankeerberghen, M.; Ponsard, B.

    1999-01-01

    Operation and utilization of the materials testing reactor BR2 at the Belgian Nuclear Research Centre (SCK·CEN) has since its start in 1963 always followed closely the needs and developments of nuclear technology. In particular, a multitude of irradiation experiments have been carried out for most types of nuclear power reactors, existing or under design. Since the early 1990s and increased focus was directed towards more specific irradiation testing needs for light water reactor fuels and materials, although other areas of utilization continued as well (e.g. fusion reactor materials, safety research, ...), including also the growing activities of radioisotope production and silicon doping. An important milestone was the decision in 1994 to implement a comprehensive refurbishment programme for the BR2 reactor and plant installations. The scope of this programme comprised very substantial studies and hardware interventions, which have been completed in early 1997 within planning and budget. Directly connected to this strategic decision for reactor refurbishment was the reinforcement of our efforts to requalify and upgrade the existing irradiation facilities and to develop advanced devices in BR2 to support emerging programs in the following fields: - LWR pressure vessel steel, - LWR irradiation assisted stress corrosion cracking (IASCC), - reliability and safety of high-burnup LWR fuel, - fusion reactor materials and blanket components, - fast neutron reactor fuels and actinide burning, - extension and diversification of radioisotope production. The paper highlights these advances in the areas of BR2 utilisation and the ongoing development activities for the required new generation of irradiations devices. (author)

  18. An improved thermal-hydraulic modeling of the Jules Horowitz Reactor using the CATHARE2 system code

    Energy Technology Data Exchange (ETDEWEB)

    Pegonen, R., E-mail: pegonen@kth.se [KTH Royal Institute of Technology, Roslagstullsbacken 21, SE-10691 Stockholm (Sweden); Bourdon, S.; Gonnier, C. [CEA, DEN, DER, SRJH, CEA Cadarache, 13108 Saint-Paul-lez-Durance Cedex (France); Anglart, H. [KTH Royal Institute of Technology, Roslagstullsbacken 21, SE-10691 Stockholm (Sweden)

    2017-01-15

    Highlights: • An improved thermal-hydraulic modeling of the JHR reactor is described. • Thermal-hydraulics of the JHR is analyzed during loss of flow accident. • The heat exchanger approach gives more realistic and less conservative results. - Abstract: The newest European high performance material testing reactor, the Jules Horowitz Reactor, will support current and future nuclear reactor designs. The reactor is under construction at the CEA Cadarache research center in southern France and is expected to achieve first criticality at the end of this decade. This paper presents an improved thermal-hydraulic modeling of the reactor using solely CATHARE2 system code. Up to now, the CATHARE2 code was simulating the full reactor with a simplified approach for the core and the boundary conditions were transferred into the three-dimensional FLICA4 core simulation. A new more realistic methodology is utilized to analyze the thermal-hydraulic simulation of the reactor during a loss of flow accident.

  19. Hybrid reactors

    International Nuclear Information System (INIS)

    Moir, R.W.

    1980-01-01

    The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

  20. Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966; 2. Jugoslovenski simpozijum iz reaktorske fizike, Deo 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1966-07-01

    This Volume 2 of the Proceedings of 2. Yugoslav symposium on reactor physics includes eight papers dealing with the following topics: method for measuring high anti reactivities of a reactor system; integration method for thermal reaction rate calculation; Determination of initial core configuration for BHWR-200 MWe; safety shutdowns and failures of the RA reactor equipment; determining the reactivity of absorption rods; measurements of thermal and fast neutron fluxes at the TRIGA reactor and other measurements during operation of the TRIGA reactor; mathematical modelling of the reactor safety; review of problems and methods for radiation risk assessment in the environment of a nuclear power plant.

  1. Magnetic Field-Vector Measurements in Quiescent Prominences via the Hanle Effect: Analysis of Prominences Observed at Pic-Du-Midi and at Sacramento Peak

    Science.gov (United States)

    Bommier, V.; Leroy, J. L.; Sahal-Brechot, S.

    1985-01-01

    The Hanle effect method for magnetic field vector diagnostics has now provided results on the magnetic field strength and direction in quiescent prominences, from linear polarization measurements in the He I E sub 3 line, performed at the Pic-du-Midi and at Sacramento Peak. However, there is an inescapable ambiguity in the field vector determination: each polarization measurement provides two field vector solutions symmetrical with respect to the line-of-sight. A statistical analysis capable of solving this ambiguity was applied to the large sample of prominences observed at the Pic-du-Midi (Leroy, et al., 1984); the same method of analysis applied to the prominences observed at Sacramento Peak (Athay, et al., 1983) provides results in agreement on the most probable magnetic structure of prominences; these results are detailed. The statistical results were confirmed on favorable individual cases: for 15 prominences observed at Pic-du-Midi, the two-field vectors are pointing on the same side of the prominence, and the alpha angles are large enough with respect to the measurements and interpretation inaccuracies, so that the field polarity is derived without any ambiguity.

  2. Análisis comparativo de la situación actual de los puertos secos en tres contextos diferentes: Colombia, México, España

    OpenAIRE

    Rozo Alvarado, Jonathan Efrain

    2013-01-01

    El presente trabajo tiene como finalidad analizar y comparar Puertos Secos en tres países diferentes: Colombia, México y España; y con ello determinar las claves o herramientas para el éxito de estos. Para esto, la investigación se llevó a cabo a nivel documental y teórico, abarcando desde documentos de investigación académicos y de entidades supranacionales, hasta documentos de carácter legislativo de diferente orden, para los tres países de estudio, incluyendo estudios privados y herramient...

  3. Problems of nuclear reactor safety. Vol. 2

    International Nuclear Information System (INIS)

    Goncharov, L.A.

    1995-01-01

    Theses of proceedings of the 9 Topical Meeting on problems of nuclear power plant safety are presented. Reports include results of neutron-physical experiments carried out for reactor safety justification. Concepts of advanced reactors with improved safety are considered. Results of researches on fuel cycles are given too

  4. The Effect Of Beryllium Interaction With Fast Neutrons On the Reactivity Of ETRR-2 Research Reactor

    International Nuclear Information System (INIS)

    Aziz, M.; El Messiry, A.M.

    2000-01-01

    The effect of beryllium interactions with fast neutrons is studied for Etrr 2 research reactors. Isotope build up inside beryllium blocks is calculated under different irradiation times. a new model for the Etrr 2 research reactor is designed using MCNP code to calculate the reactivity and flux change of the reactor due to beryllium poison

  5. Economics and utilization of thorium in nuclear reactors. Technical annexes 1 and 2

    International Nuclear Information System (INIS)

    1978-05-01

    An assessment of the impact of utilizing the 233 U/thorium fuel cycle in the U.S. nuclear economy is strongly dependent upon several decisions involving nuclear energy policy. These decisions include: (1) to recycle or not recycle fissile material; (2) if fissile material is recycled, to recycle plutonium, 233 U, or both; and (3) to deploy or not to deploy advanced reactor designs such as Fast Breeder Reactors (FBR's), High Temperature Gas Reactors (HTGR's), and Canadian Deuterium Uranium Reactors (CANDU's). This report examines the role of thorium in the context of the above policy decisions while focusing special attention on economics and resource utilization

  6. Development of UO2/PuO2 dispersed in uranium matrix CERMET fuel system for fast reactors

    International Nuclear Information System (INIS)

    Sinha, V.P.; Hegde, P.V.; Prasad, G.J.; Pal, S.; Mishra, G.P.

    2012-01-01

    CERMET fuel with either PuO 2 or enriched UO 2 dispersed in uranium metal matrix has a strong potential of becoming a fuel for the liquid metal cooled fast breeder reactors (LMR’s). In fact it may act as a bridge between the advantages and disadvantages associated with the two extremes of fuel systems (i.e. ceramic fuel and metallic fuel) for fast reactors. At Bhabha Atomic Research Centre (BARC), R and D efforts are on to develop this CERMET fuel by powder metallurgy route. This paper describes the development of flow sheet for preparation of UO 2 dispersed in uranium metal matrix pellets for three different compositions i.e. U–20 wt%UO 2 , U–25 wt%UO 2 and U–30 wt%UO 2 . It was found that the sintered pellets were having excellent integrity and their linear mass was higher than that of carbide fuel pellets used in Fast Breeder Test Reactor programme (FBTR) in India. The pellets were characterized by X-ray diffraction (XRD) technique for phase analysis and lattice parameter determination. The optical microstructures were developed and reported for all the three different U–UO 2 compositions.

  7. Development of UO2/PuO2 dispersed in uranium matrix CERMET fuel system for fast reactors

    Science.gov (United States)

    Sinha, V. P.; Hegde, P. V.; Prasad, G. J.; Pal, S.; Mishra, G. P.

    2012-08-01

    CERMET fuel with either PuO2 or enriched UO2 dispersed in uranium metal matrix has a strong potential of becoming a fuel for the liquid metal cooled fast breeder reactors (LMR's). In fact it may act as a bridge between the advantages and disadvantages associated with the two extremes of fuel systems (i.e. ceramic fuel and metallic fuel) for fast reactors. At Bhabha Atomic Research Centre (BARC), R & D efforts are on to develop this CERMET fuel by powder metallurgy route. This paper describes the development of flow sheet for preparation of UO2 dispersed in uranium metal matrix pellets for three different compositions i.e. U-20 wt%UO2, U-25 wt%UO2 and U-30 wt%UO2. It was found that the sintered pellets were having excellent integrity and their linear mass was higher than that of carbide fuel pellets used in Fast Breeder Test Reactor programme (FBTR) in India. The pellets were characterized by X-ray diffraction (XRD) technique for phase analysis and lattice parameter determination. The optical microstructures were developed and reported for all the three different U-UO2 compositions.

  8. Utilization of the SLOWPOKE-2 research reactor

    International Nuclear Information System (INIS)

    Lalor, G.C.

    2001-01-01

    SLOWPOKEs are typically low power research reactors that have a limited number of applications. However, a significant range of NAA can be performed with such reactors. This paper describes a SLOWPOKE-based NAA program that is performing a valuable series of studies in Jamaica, including geological mapping and pollution assessment. (author)

  9. Alteration in reactor installations (Unit 1 and 2 reactor facilities) in the Hamaoka Nuclear Power Station of The Chubu Electric Power Co., Inc. (report)

    International Nuclear Information System (INIS)

    1982-01-01

    A report by the Nuclear Safety Commission to the Ministry of International Trade and Industry concerning the alteration in Unit 1 and 2 reactor facilities in the Hamaoka Nuclear Power Station, Chubu Electric Power Co., Inc., was presented. The technical capabilities for the alteration of reactor facilities in Chubu Electric Power Co., Inc., were confirmed to be adequate. The safety of the reactor facilities after the alteration was confirmed to be adequate. The items of examination made for the confirmation of the safety are as follows: reactor core design (nuclear design, mechanical design, mixed reactor core), the analysis of abnormal transients in operation, the analysis of various accidents, the analysis of credible accidents for site evaluation. (Mori, K.)

  10. Caracterización de jamones adicionados con pastas residuales de la extracción mecánica de aceite de frutos secos

    Directory of Open Access Journals (Sweden)

    Juan José Luna Guevara

    2013-01-01

    Full Text Available Los frutos secos contienen en su composición nutrientes y compuestos bioactivos que al ser consumidos en cantidades suficientes aportan beneficios a la salud. En este estudio se evaluó la influencia de la adición de pastas residuales (10 %, obtenidas de la extracción de aceite de nuez de Castilla (Juglans regia L., nuez pecanera (Carya illinoinensis (Wangenh. K. Koch, variedad Western Shley, y cacahuate (Arachis hypogaea, sobre la modificación de algunas características de textura, composición proximal, fisicoquímicas, microbiológicas y sensoriales en jamones cocidos. Los jamones estudiados fueron almacenados a 4 °C durante 21 días. Las pastas adicionadas a los jamones aumentaron de manera significativa (P≤0,05 el contenido de proteína, grasa y fibra total. Los jamones adicionados con pasta presentaron estructuras menos rígidas (P≤0,05. Los parámetros de color (L*, a* y b* de los jamones mostraron una ligera disminución durante el tiempo de almacenamiento, a excepción de los adicionados con nuez de Castilla que mostraron un mayor oscurecimiento. Las pastas de frutos secos contribuyeron significativamente (P≤ 0,05 a disminuir la vida de anaquel de los jamones. Sin embargo, el recuento de mohos y levaduras en los jamones fue menor a 10 UFC/g a los 21 días de almacenamiento. La aw y el pH disminuyeron significativamente (P≤0,05 y la sinéresis aumentó durante el almacenamiento. Los jamones adicionados con pastas residuales fueron sensorialmente bien aceptados con respecto al color, olor, sabor, apariencia y aceptabilidad general.

  11. Objetivación en el diagnóstico del síndrome de ojo seco. Correlación entre pruebas clínicas

    OpenAIRE

    Pena Verdeal, Hugo

    2016-01-01

    Mantener la estructura y función de la película lagrimal es esencial para que pueda existir una correcta visión y confort ocular. El Síndrome de Ojo Seco (SOS) es una enfermedad de la unidad funcional lagrimal con un diagnóstico controvertido cuya prevalencia ha aumentado mucho en los últimos años, influyendo a la calidad visual y calidad de vida de las personas. La principal finalidad del presente trabajo es objetivizar tests clínicos de diagnóstico de SOS mediante técnicas semiautomática...

  12. Measurements at the RA Reactor related to the VISA-2 project - Part 1, Start-up of the RA reactor and measurement of new RA reactor core parameters

    International Nuclear Information System (INIS)

    Markovic, H.

    1962-07-01

    The objective of the measurements was determining the neutron flux in the RA reactor core. Since the number of fuel channels is increased from 56 to 68 within the VISA-2 project, it was necessary to attain criticality of the RA reactor and measure the neutron flux properties. The 'program of RA reactor start-up' has been prepared separately and it is included in this report. Measurements were divided in two phases. First phase was measuring of the neutron flux after the criticality was achieved but at zero power. During phase two measurements were repeated at several power levels, at equilibrium xenon poisoning. This report includes experimental data of flux distributions and absolute values of the thermal and fast neutron flux in the RA reactor experimental channels and values of cadmium ratio for determining the neutron epithermal flux. Data related to calibration of regulatory rods for cold un poisoned core are included [sr

  13. Reactor limitation system improves the safety and availability of the Angra 2 nuclear power plant

    International Nuclear Information System (INIS)

    Souza Mendes, J.E. de

    1987-01-01

    Beyond the classic Reactor Protection System and Reactor Control System, nuclear plant Angra 2 has a third system called Reactor Limitation System which combines the intelligence features of the control systems with the high reliability of the protection systems. In determined events, which are not controlled by the control system (e.g.: load rejection, failure of one main reactor coolant pump), the Reactor Limitation System actuates automatically in order to lead the plant to a safe operating condition and so it avoids the actuation of the Reactor Protection System and consequently the reactor trip. This increases safety and availability of the plant and reduces component stresses. After the safe operating condition is reached, the process guidance automatically returns to the control systems. (Author) [pt

  14. CO_2 capture with solid sorbent: CFD model of an innovative reactor concept

    International Nuclear Information System (INIS)

    Barelli, L.; Bidini, G.; Gallorini, F.

    2016-01-01

    Highlights: • A new reactor solution based on rotating fixed beds was presented. • The preliminary design of the reactor was approached. • A CFD model of the reactor, including CO_2 capture kinetic, was developed. • The CFD model is validated with experimental results. • Sorbent exploitation increasing is possible thanks to the new reactor. - Abstract: In future decarbonization scenarios, CCS with particular reference to post-combustion technologies will be an important option also for energy intensive industries. Nevertheless, today CCS systems are rarely installed due to high energy and cost penalties of current technology based on chemical scrubbing with amine solvent. Therefore, innovative solutions based on new/optimized solvents, sorbents, membranes and new process designs, are R&D priorities. Regarding the CO_2 capture through solid sorbents, a new reactor solution based on rotating fixed beds is presented in this paper. In order to design the innovative system, a suitable CFD model was developed considering also the kinetic capture process. The model was validated with experimental results obtained by the authors in previous research activities, showing a potential reduction of energy penalties respect to current technologies. In the future, the model will be used to identify the control logic of the innovative reactor in order to verify improvements in terms of sorbent exploitation and reduction of system energy consumption.

  15. MULTI-LOOP CONTROL DESIGN IN MULTIVARIABLE (2X2 CONTINUOUS STIRRED TANK REACTOR

    Directory of Open Access Journals (Sweden)

    Abdul Wahid

    2015-06-01

    Full Text Available With this study, the design and tuning of multi-loop for multivariable (2x2 CSTR will be made in order to achieve optimum CSTR control performance. This study used Bequette model reactor and MATLAB software and is expected to be able to cope with disturbances in the reactor so that the reactor system is able to stabilize quickly despite the distractions. In this study, the design will be made using multi-loop approach, along with PI controller as the next step. Then, BLT and auto-tune tuning method will be used in PI controller and given disturbances to both of tuning method. The controller performances are then compared. Results of the study are then analyzed for discussions and conclusions. Results from this study have shown that in terms of disturbance rejection, BLT is better than auto-tune based on comparison between both of controller performances. For IAE for the case of temperature, BLT is 30% better than auto-tune, but it is almost the same for the case of concentration. For settling time for the case of concentration, BLT is 30% better than auto-tune, and for the case of temperature, BLT is 18% better than auto-tune. For rise time for the case of concentration and temperature, BLT is 30% better than auto-tune.

  16. Operating reactors licensing actions summary. Volume 5, No. 2

    International Nuclear Information System (INIS)

    1985-04-01

    The Operating Reactors Licensing Actions Summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Resource Management. This summary report is published primarily for internal NRC use in managing the Operating Reactors Licensing Actions Program

  17. Tests of Neutron Spectrum Calculations with the Help of Foil Measurements in a D{sub 2}O and in an H{sub 2}O-Moderated Reactor and in Reactor Shields of Concrete an Iron

    Energy Technology Data Exchange (ETDEWEB)

    Nilsson, R; Aalto, E

    1964-09-15

    Foil measurements covering the fast, epithermal and thermal neutron energy regions have been made in the centre of the Swedish D{sub 2}O-moderated reactor R1, in the pool reactor R2-0, and in different positions in reactor shields of iron, magnetite concrete and ordinary concrete. Neutron spectra have also been calculated for most of these positions, often with the help of a numerical integration of the Boltzmann equation. The measurements and the calculated spectra are presented.

  18. Microflow photochemistry: UVC-induced [2 + 2]-photoadditions to furanone in a microcapillary reactor

    Directory of Open Access Journals (Sweden)

    Sylvestre Bachollet

    2013-10-01

    Full Text Available [2 + 2]-Cycloadditions of cyclopentene and 2,3-dimethylbut-2-ene to furanone were investigated under continuous-flow conditions. Irradiations were conducted in a FEP-microcapillary module which was placed in a Rayonet chamber photoreactor equipped with low wattage UVC-lamps. Conversion rates and isolated yields were compared to analogue batch reactions in a quartz test tube. In all cases examined, the microcapillary reactor furnished faster conversions and improved product qualities.

  19. A simulation Model of the Reactor Hall Ventilation and air Conditioning Systems of ETRR-2

    International Nuclear Information System (INIS)

    Abd El-Rahman, M.F.

    2004-01-01

    Although the conceptual design for any system differs from one designer to another. each of them aims to achieve the function of the system required. the ventilation and air conditioning system of reactors hall is one of those systems that really differs but always dose its function for which it is designed. thus, ventilation and air conditioning in some reactor hall constitute only one system whereas in some other ones, they are separate systems. the Egypt Research Reactor-2 (ETRR-2)represents the second type. most studies conducted on ventilation and air conditioning simulation models either in traditional building or for research rectors show that those models were not designed similarly to the model of the hall of ETRR-2 in which ventilation and air conditioning constitute two separate systems.besides, those studies experimented on ventilation and air conditioning simulation models of reactor building predict the temperature and humidity inside these buildings at certain outside condition and it is difficult to predict when the outside conditions are changed . also those studies do not discuss the influences of reactor power changes. therefore, the present work deals with a computational study backed by infield experimental measurements of the performance of the ventilation and air conditioning systems of reactor hall during normal operation at different outside conditions as well as at different levels of reactor power

  20. Thermal design of heat-exchangeable reactors using a dry-sorbent CO2 capture multi-step process

    International Nuclear Information System (INIS)

    Moon, Hokyu; Yoo, Hoanju; Seo, Hwimin; Park, Yong-Ki; Cho, Hyung Hee

    2015-01-01

    The present study proposes a multi-stage CO 2 capture process that incorporates heat-exchangeable fluidized-bed reactors. For continuous multi-stage heat exchange, three dry regenerable sorbents: K 2 CO 3 , MgO, and CaO, were used to create a three-stage temperature-dependent reaction chain for CO 2 capture, corresponding to low (50–150 °C), middle (350–650 °C), and high (750–900 °C) temperature stages, respectively. Heat from carbonation in the high and middle temperature stages was used for regeneration for the middle and low temperature stages. The feasibility of this process is depending on the heat-transfer performance of the heat-exchangeable fluidized bed reactors as the focus of this study. The three-stage CO 2 capture process for a 60 Nm 3 /h CO 2 flow rate required a reactor area of 0.129 and 0.130 m 2 for heat exchange between the mid-temperature carbonation and low-temperature regeneration stages and between the high-temperature carbonation and mid-temperature regeneration stages, respectively. The reactor diameter was selected to provide dense fluidization conditions for each bed with respect to the desired flow rate. The flow characteristics and energy balance of the reactors were confirmed using computational fluid dynamics and thermodynamic analysis, respectively. - Highlights: • CO 2 capture process is proposed using a multi-stage process. • Reactor design is conducted considering heat exchangeable scheme. • Reactor surface is designed by heat transfer characteristics of fluidized bed

  1. Increased SRP reactor power

    International Nuclear Information System (INIS)

    MacAfee, I.M.

    1983-01-01

    Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

  2. Core design calculations of IRIS reactor using modified CORD-2 code package

    International Nuclear Information System (INIS)

    Pevec, D.; Grgic, D.; Jecmenica, R.; Petrovic, B.

    2002-01-01

    Core design calculations, with thermal-hydraulic feedback, for the first cycle of the IRIS reactor were performed using the modified CORD-2 code package. WIMSD-5B code is applied for cell and cluster calculations with two different 69-group data libraries (ENDF/BVI rev. 5 and JEF-2.2), while the nodal code GNOMER is used for diffusion calculations. The objective of the calculation was to address basic core design problems for innovative reactors with long fuel cycle. The results were compared to our results obtained with CORD-2 before the modification and to preliminary results obtained with CASMO code for a similar problem without thermal-hydraulic feedback.(author)

  3. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2002-01-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

  4. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  5. Reactor Physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, A.

    2001-01-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

  6. BR2 reactor: medical and industrial applications

    International Nuclear Information System (INIS)

    Ponsard, B.

    2005-01-01

    The radioisotopes are produced for various applications in the nuclear medicine (diagnostic, therapy, palliation of metastatic bone pain), industry (radiography of welds, ...), agriculture (radiotracers, ...) and basic research. Due to the availability of high neutron fluxes (thermal neutron flux up to 10 15 n/cm 2 .s), the BR2 reactor is considered as a major facility through its contribution for a continuous supply of products such 99 Mo ( 99 mTc), 131 I, 133 Xe, 192 Ir, 186 Re, 153 Sm, 90 Y, 32 P, 188 W ( 188 Re), 203 Hg, 82 Br, 41 Ar, 125 I, 177 Lu, 89 Sr, 60 Co, 169 Yb, 147 Nd, and others. Neutron Transmutation Doped (NTD) silicon is produced for the semiconductor industry in the SIDONIE (Silicon Doping by Neutron Irradiation Experiment) facility, which is designed to continuously rotate and traverse the silicon through the neutron flux. These combined movements produce exceptional dopant homogeneity in batches of silicon measuring 4 and 5-inches in diameter by up to 750 mm in length. The main objectives of work performed were to provide a reliable and qualitative supply of radioisotopes and NTD-silicon to the customers in accordance with a quality system that has been certified to the requirements of the EN ISO 9001: 2000. This new Quality System Certificate has been obtained in November 2003 for the Production of radioisotopes for medical and industrial applications and the Production of Neutron Transmutation Doped (NTD) Silicon in the BR2 reactor

  7. Possible future roles for fast breeder reactors Part 1 and 2

    International Nuclear Information System (INIS)

    1978-06-01

    Part 1. The Fast Breeder Reactor (in particular in its sodium cooled version) has been steadily developed in the Community. This report attempts to quantify the advantages of this system in terms of fossil energy and uranium savings in the medium/long term as well as to examine some long term economic implications. The methodology of comparing scenarios, not individual reactor systems is followed. These scenarios have been chosen taking into account a range of assumptions concerning Community energy demand growth, fossil energy and uranium availability and technological capabilities. Part 2. The fast breeder reactor (FBR), particularly its sodium-cooled form (LMFBR) has been under development in the Community for many years. Industrial enterprises dedicated to its commercialisation have been formed and long range plans for its industrial utilisation are being formulated. The value of breeder reactors from the point of view of minimising Community fuel requirements has been discussed in Part I of this report (1). In Part II the consequences of delaying their introduction, and the demands placed upon the recycle industry by the introduction of fast reactors of different characteristics, using the Community electricity demand scenarios developed for Part I, are discussed. In addition comments are provided upon the effect of FBR introduction on the size of plutonium stocks

  8. Diversity of Genetic Resources and Genetic Association Analyses of Green and Dry Chillies of Eastern India Diversidad de Recursos Genéticos y Análisis de Asociación Genética de Ajíes Verdes y Secos del Este de India

    Directory of Open Access Journals (Sweden)

    Arup Chattopadhyay

    2011-09-01

    Full Text Available Chilli (Capsicum annuum L. is regarded as one of the main commercial vegetable and spice crops at the global level. Maximum diversity can be noted among the cultivars/landraces available in India with respect to shape, size, yield, quality, and other traits. The present experiment was conducted to identify the most promising chilli variety suited for green and dry purposes, to study the genetic variability for different traits and to assess the association of different yield attributing traits with the green and dry yield of chilli. Thirty four genotypes were characterized during a 2-yr period. Most of the genotypes possessed the character constellation of C. annuum. Two genotypes, ‘Chaitali Pointed’ and ‘BC CH Sel-4’ were found most promising with respect to green fruit yield (272.79 g, 221.10 g per plant and dry fruit yield (54.56 g, 44.44 g per plant. Phenotypic and Genotypic Coefficient of Variation values for green fruit weight (119.95%, 111.26%, green fruit girth (89.76%, 48.93%, weight of red ripe fruit (112.02%, 111.93%, weight of dry fruit (111.63%, 110.97% and number of fruits per plant (86.05%, 85.02% were recorded to be high. Green fruit yield per plant, ascorbic acid content, and number of fruits per plant also showed very high broad-sense heritability and genetic advance. From the study of correlation and path coefficient analyses, the number of fruits per plant, green fruit length for green chilli, weight of dry fruit and the number of fruits per plant for dry chilli were found to the most important selection indices.El ají (Capsicum annuum L. es considerado como uno de los principales cultivos comerciales de vegetales y especias a nivel mundial. La máxima diversidad puede ser observada entre los cultivares y razas disponibles en India con respecto a forma, tamaño, producción, calidad, y otros rasgos. Este experimento se realizó para identificar la variedad de ají más promisoria y apropiada para fruto verde y seco

  9. A regression approach for Zircaloy-2 in-reactor creep constitutive equations

    International Nuclear Information System (INIS)

    Yung Liu, Y.; Bement, A.L.

    1977-01-01

    In this paper the methodology of multiple regressions as applied to Zircaloy-2 in-reactor creep data analysis and construction of constitutive equation are illustrated. While the resulting constitutive equation can be used in creep analysis of in-reactor Zircaloy structural components, the methodology itself is entirely general and can be applied to any creep data analysis. The promising aspects of multiple regression creep data analysis are briefly outlined as follows: (1) When there are more than one variable involved, there is no need to make the assumption that each variable affects the response independently. No separate normalizations are required either and the estimation of parameters is obtained by solving many simultaneous equations. The number of simultaneous equations is equal to the number of data sets. (2) Regression statistics such as R 2 - and F-statistics provide measures of the significance of regression creep equation in correlating the overall data. The relative weights of each variable on the response can also be obtained. (3) Special regression techniques such as step-wise, ridge, and robust regressions and residual plots, etc., provide diagnostic tools for model selections. Multiple regression analysis performed on a set of carefully selected Zircaloy-2 in-reactor creep data leads to a model which provides excellent correlations for the data. (Auth.)

  10. Coolant radiolysis studies in the high temperature, fuelled U-2 loop in the NRU reactor

    International Nuclear Information System (INIS)

    Elliot, A.J.; Stuart, C.R.

    2008-06-01

    An understanding of the radiolysis-induced chemistry in the coolant water of nuclear reactors is an important key to the understanding of materials integrity issues in reactor coolant systems. Significant materials and chemistry issues have emerged in Pressurized Water Reactors (PWR), Boiling Water Reactors (BWR) and CANDU reactors that have required a detailed understanding of the radiation chemistry of the coolant. For each reactor type, specific computer radiolysis models have been developed to gain insight into radiolysis processes and to make chemistry control adjustments to address the particular issue. In this respect, modelling the radiolysis chemistry has been successful enough to allow progress to be made. This report contains a description of the water radiolysis tests performed in the U-2 loop, NRU reactor in 1995, which measured the CHC under different physical conditions of the loop such as temperature, reactor power and steam quality. (author)

  11. Design and computational analysis of passive siphon breaker for 49-2 swimming pool reactor

    International Nuclear Information System (INIS)

    Yue Zhiting; Song Yunpeng; Liu Xingmin; Zou Yao; Wu Yuanyuan

    2014-01-01

    Based on safety considerations, a passive siphon breaker will be added to the primary cooling system of 49-2 Swimming Pool Reactor (SPR). With the breaker location determined, the capability of siphon breakers with diameters of 1.5 cm and 2.0 cm was calculated and analyzed respectively by RELAP5/MOD3.3 code. The results show that in the condition of large break loss of coolant accident these two sizes of siphon breakers are able to break the siphon phenomena, and maintain the pool water level above the reactor core when the reactor and the pump are shutdown. In the end, to be conservative, the siphon breaker with diameter of 2.0 cm is adopted. (authors)

  12. Criticality and shielding calculations for containers in dry of spent fuel of TRIGA Mark III reactor of ININ; Calculos de criticidad y blindaje para contenedores en seco de combustible gastado del reactor Triga Mark III del ININ

    Energy Technology Data Exchange (ETDEWEB)

    Barranco R, F.

    2015-07-01

    In this thesis criticality and shielding calculations to evaluate the design of a container of dry storage of spent nuclear fuel generated in research reactors were made. The design of such container was originally proposed by Argentina and Brazil, and the Instituto Nacional de Investigaciones Nucleares (ININ) of Mexico. Additionally, it is proposed to modify the design of this container to store spent fuel 120 that are currently in the pool of TRIGA Mark III reactor, the Nuclear Center of Mexico and calculations and analyzes are made to verify that the settlement of these fuel elements is subcritical limits and dose rates to workers and the general public are not exceeded. These calculations are part of the design criteria for security protection systems in dry storage system (Dss for its acronym in English) proposed by the Nuclear Regulatory Commission (NRC) of the United States. To carry out these calculations simulation codes of Monte Carlo particle transport as MCNPX and MCNP5 were used. The initial design (design 1) 78 intended to store spent fuel with a maximum of 115. The ININ has 120 fuel elements and spent 3 control rods (currently stored in the reactor pool). This leads to the construction of two containers of the original design, but for economic reasons was decided to modify (design 2) to store in a single container. Criticality calculations are performed to 78, 115 and fresh fuel elements 124 within the container, to the two arrangements described in Chapter 4, modeling the three-dimensional geometry assuming normal operating conditions and accident. These calculations are focused to demonstrate that the container will remain subcritical, that is, that the effective multiplication factor is less than 1, in particular not greater than 0.95 (as per specified by the NRC). Spent fuel 78 and 124 within the container, both gamma radiation to neutron shielding calculations for only two cases were simulated. First actinides and fission products generated

  13. Efficient H2O2/CH3COOH oxidative desulfurization/denitrification of liquid fuels in sonochemical flow-reactors.

    Science.gov (United States)

    Calcio Gaudino, Emanuela; Carnaroglio, Diego; Boffa, Luisa; Cravotto, Giancarlo; Moreira, Elizabeth M; Nunes, Matheus A G; Dressler, Valderi L; Flores, Erico M M

    2014-01-01

    The oxidative desulfurization/denitrification of liquid fuels has been widely investigated as an alternative or complement to common catalytic hydrorefining. In this process, all oxidation reactions occur in the heterogeneous phase (the oil and the polar phase containing the oxidant) and therefore the optimization of mass and heat transfer is of crucial importance to enhancing the oxidation rate. This goal can be achieved by performing the reaction in suitable ultrasound (US) reactors. In fact, flow and loop US reactors stand out above classic batch US reactors thanks to their greater efficiency and flexibility as well as lower energy consumption. This paper describes an efficient sonochemical oxidation with H2O2/CH3COOH at flow rates ranging from 60 to 800 ml/min of both a model compound, dibenzotiophene (DBT), and of a mild hydro-treated diesel feedstock. Four different commercially available US loop reactors (single and multi-probe) were tested, two of which were developed in the authors' laboratory. Full DBT oxidation and efficient diesel feedstock desulfurization/denitrification were observed after the separation of the polar oxidized S/N-containing compounds (S≤5 ppmw, N≤1 ppmw). Our studies confirm that high-throughput US applications benefit greatly from flow-reactors. Copyright © 2013 Elsevier B.V. All rights reserved.

  14. Direct In Situ Quantification of HO2 from a Flow Reactor.

    Science.gov (United States)

    Brumfield, Brian; Sun, Wenting; Ju, Yiguang; Wysocki, Gerard

    2013-03-21

    The first direct in situ measurements of hydroperoxyl radical (HO2) at atmospheric pressure from the exit of a laminar flow reactor have been carried out using mid-infrared Faraday rotation spectroscopy. HO2 was generated by oxidation of dimethyl ether, a potential renewable biofuel with a simple molecular structure but rich low-temperature oxidation chemistry. On the basis of the results of nonlinear fitting of the experimental data to a theoretical spectroscopic model, the technique offers an estimated sensitivity of reactor exit temperature range of 398-673 K. Accurate in situ measurement of this species will aid in quantitative modeling of low-temperature and high-pressure combustion kinetics.

  15. Reactor science and technology: operation and control of reactors

    International Nuclear Information System (INIS)

    Qiu Junlong

    1994-01-01

    This article is a collection of short reports on reactor operation and research in China in 1991. The operation of and research activities linked with the Heavy Water Research Reactor, Swimming Pool Reactor and Miniature Neutron Source Reactor are briefly surveyed. A number of papers then follow on the developing strategies in Chinese fast breeder reactor technology including the conceptual design of an experimental fast reactor (FFR), theoretical studies of FFR thermo-hydraulics and a design for an immersed sodium flowmeter. Reactor physics studies cover a range of topics including several related to work on zero power reactors. The section on reactor safety analysis is concerned largely with the assessment of established, and the presentation of new, computer codes for use in PWR safety calculations. Experimental and theoretical studies of fuels and reactor materials for FBRs, PWRs, BWRs and fusion reactors are described. A final miscellaneous section covers Mo-Tc isotope production in the swimming pool reactor, convective heat transfer in tubes and diffusion of tritium through plastic/aluminium composite films and Li 2 SiO 3 . (UK)

  16. Status and perspective of development of cold moderators at the IBR-2 reactor

    International Nuclear Information System (INIS)

    Kulikov, S; Shabalin, E

    2012-01-01

    The modernized IBR-2M reactor will start its operation with three water grooved moderators in 2011. Afterwards, they will be exchanged by a new complex of moderators. The complex consists of three so-called kombi-moderators, each of them containing a pre-moderator, a cold moderator, grooved ambient water moderators and post-moderators. They are mounted onto three moveable trolleys that serve to deliver and install moderators near the reactor core. The project is divided in three stages. In 2012 the first stage of development of complex of moderators will be finished. The water grooved moderator will be replaced with the new kombi-moderator for beams nos. 7, 8, 10, 11. Main parameters of moderators for this direction will be studied then. The next stages will be done for beams nos. 2-3 and for beams nos. 1, 9, 4-6, consequently. Cold moderator chambers at the modernized IBR-2 reactor are filled with thousands of beads (∼3.5 - 4 mm in diameter) of moderating material. The cold helium gas flow delivers beads from the charging device to the moderator during the fulfillment process and cools down them during the reactor cycle. The mixture of aromatic hydrocarbons (mesithylen and m-xylen) has been chosen as moderating material. The explanation of the choice of material for novel cold neutron moderators, configuration of moderator complex for the modernized IBR-2 reactor and the main results of optimization of moderator complex for the third stage of moderator development are discussed in the article.

  17. Status and perspective of development of cold moderators at the IBR-2 reactor

    Science.gov (United States)

    Kulikov, S.; Shabalin, E.

    2012-03-01

    The modernized IBR-2M reactor will start its operation with three water grooved moderators in 2011. Afterwards, they will be exchanged by a new complex of moderators. The complex consists of three so-called kombi-moderators, each of them containing a pre-moderator, a cold moderator, grooved ambient water moderators and post-moderators. They are mounted onto three moveable trolleys that serve to deliver and install moderators near the reactor core. The project is divided in three stages. In 2012 the first stage of development of complex of moderators will be finished. The water grooved moderator will be replaced with the new kombi-moderator for beams #7, 8, 10, 11. Main parameters of moderators for this direction will be studied then. The next stages will be done for beams #2-3 and for beams #1, 9, 4-6, consequently. Cold moderator chambers at the modernized IBR-2 reactor are filled with thousands of beads (~3.5 - 4 mm in diameter) of moderating material. The cold helium gas flow delivers beads from the charging device to the moderator during the fulfillment process and cools down them during the reactor cycle. The mixture of aromatic hydrocarbons (mesithylen and m-xylen) has been chosen as moderating material. The explanation of the choice of material for novel cold neutron moderators, configuration of moderator complex for the modernized IBR-2 reactor and the main results of optimization of moderator complex for the third stage of moderator development are discussed in the article.

  18. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

  19. Loss-of-Flow and Loss-of-Pressure Simulations of the BR2 Research Reactor with HEU and LEU Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Licht, J. [Argonne National Lab. (ANL), Argonne, IL (United States); Bergeron, A. [Argonne National Lab. (ANL), Argonne, IL (United States); Dionne, B. [Argonne National Lab. (ANL), Argonne, IL (United States); Sikik, E. [Belgian Nuclear Research Center (SCK-CEN), Mol (Belgium); Van den Branden, G. [Belgian Nuclear Research Center (SCK-CEN), Mol (Belgium); Koonen, E. [Belgian Nuclear Research Center (SCK-CEN), Mol (Belgium)

    2016-01-01

    Belgian Reactor 2 (BR2) is a research and test reactor located in Mol, Belgium and is primarily used for radioisotope production and materials testing. The Materials Management and Minimization (M3) Reactor Conversion Program of the National Nuclear Security Administration (NNSA) is supporting the conversion of the BR2 reactor from Highly Enriched Uranium (HEU) fuel to Low Enriched Uranium (LEU) fuel. The reactor core of BR2 is located inside a pressure vessel that contains 79 channels in a hyperboloid configuration. The core configuration is highly variable as each channel can contain a fuel assembly, a control or regulating rod, an experimental device, or a beryllium or aluminum plug. Because of this variability, a representative core configuration, based on current reactor use, has been defined for the fuel conversion analyses. The code RELAP5/Mod 3.3 was used to perform the transient thermal-hydraulic safety analyses of the BR2 reactor to support reactor conversion. The input model has been modernized relative to that historically used at BR2 taking into account the best modeling practices developed by Argonne National Laboratory (ANL) and BR2 engineers.

  20. Research reactors - an overview

    International Nuclear Information System (INIS)

    West, C.D.

    1997-01-01

    A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs

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