The Windscale piles - past, present and future

International Nuclear Information System (INIS)

Jones, J.M.; Adams, A.L.

1987-01-01

The paper concerns the Windscale reactor piles, in which a fire occurred in the core of pile 1 thirty years ago. A description is given of the two Windscale piles, along with the events leading up to the accident, and the state of the piles following shutdown. The surveillance and maintenance to ensure that the pile and associated buildings were in a safe condition is outlined. The present state of the core, water ducts and pile chimneys is described. The present and future programme of work to ensure long term safety is discussed. This includes the initial steps in decommissioning of the piles. (U.K.)

Nuclear-reactor accidents: Chernobyl, TMI, and Windscale. January 1974-September 1988 (Citations from Pollution Abstracts). Report for January 1974-September 1988

International Nuclear Information System (INIS)

1988-11-01

This bibliography contains citations concerning studies and measurements of the radiological consequences of nuclear-reactor accidents. The citations cover specifically the Chernobyl reactor in the USSR, the Three Mile Island (TMI) reactor in the US, and the Windscale reactor in the UK. Included are detection and monitoring of the fallout, the resultant runoff into rivers, lakes, and the sea, the radiation effects on people, and the transfrontier radioactive contamination of the environment. (Contains 105 citations fully indexed and including a title list.)

Remote handling equipment for the decommissioning of the Windscale Advanced Gas Cooled Reactor

International Nuclear Information System (INIS)

Barker, A.; Birss, I.R.; Fish, G.

1984-01-01

A decision to decommission the Windscale Advanced Gas Cooled Reactor was taken shortly after reactor shutdown in 1981. The fuel has now been discharged and the decommissioning programme will last about 10-12 years. The paper describes the programme and objectives and deals with methods of handling and disposing of the radioactive waste material. The main new facility required is a Waste Packaging Building adjacent to the existing reactor in which the waste boxes will be filled, active waste encapsulated in concrete and the boxes cleaned, swabbed and monitored to comply with IAEA transport regulations. The handling machine concept and features are described. The assaying and packaging of the waste material, the control of box movement and the process of concrete encapsulation is described. The paper concludes with a description of the development programme to support the Project. The tasks include a study of cutting techniques, production and control of dust and smoke, viewing and lighting methods, filtration, decontamination and fixing of contamination

Experience of iodine, caesium and noble gas release from AGR failures

International Nuclear Information System (INIS)

Chapman, C.J.; Harris, A.M.; Phillips, M.E.

1985-01-01

In the event of a fuel failure in an Advanced Gas Cooled Reactor (AGR), the quantity of fission products available for release to the environment is determined by the transport of fission products in the UO 2 fuel, by the possible retention of fission products in the fuel can interspace and by the deposition of fission products on gas circuit surfaces ('plate-out'). The fission products of principal radiological concern are radioactive caesium (Cs-137 and Cs-134) and iodine (principally I-131). Results are summarised of a number of experiments which were designed to study the release of these fission products from individual fuel failures in the prototype AGR at Windscale. Results are also presented of fission product release from failures in commercial AGRs. Comparisons of measured releases of caesium and iodine relative to the release of the noble gas fission products show that, for some fuel failures, there is a significant retention of caesium and iodine within the fuel can interspace. Under normal conditions circuit deposition reduces caesium and iodine gas concentrations by several orders of magnitude. Differing release behaviour of caesium and iodine from the failures is examined together with subsequent deposition within the sampling equipment. These observations are important factors which must be considered in developing an understanding of the mechanisms involved in circuit deposition. (author)

Windscale - power versus pollution

International Nuclear Information System (INIS)

Bonney, S.

1977-01-01

Protests from British environmental groups, scientists, politicians and private citizens has forced the Government to postpone a decision on plans to create the world's largest nuclear fuel oxide reprocessing complex at Windscale, on the north-west coast of England. Subjects considered here are the vast increase in the the quantity of lethal nuclear waste stored at Windscale, the risk of explosion or plant malfunction causing radioactive fall-out, the increased radioactive discharge into the Irish Sea and into the atmosphere and the danger of terrorism or sabotage. It is stated that critics of the Windscale project have yet to be convinced that the nuclear power industry is as risk-free as its proponents maintain in public statements. To satisfy the great anxieties shared by a large number of people about the expansion plan, a full public inquiry is essential. (U.K.)

Windscale: tackling the core of the problem

International Nuclear Information System (INIS)

Anon.

1987-01-01

The decommissioning of the Windscale advanced gas-cooled reactor requires the design of a robot or manipulator to enter the reactor core and cut up the core into pieces that can then be loaded into concrete-filled boxes and disposed of as nuclear waste. Existing equipment is not entirely suitable so the machine is being designed specifically for the job. A British firm has been chosen to supply the equipment, which will have joy stick control, and will be delivered by mid 1988. Six months development work, then a year of trials will follow, before the dismantling process will start. The machine, its operation and the remote viewing provision are discussed. (U.K.)

Judgement on Windscale

International Nuclear Information System (INIS)

Roberts, G.C.; White, I.F.

1978-01-01

A summary is given of the findings of the report on the Windscale Inquiry into the application by British Nuclear Fuels Limited for planning permission to establish a plant for reprocessing irradiated oxide nuclear fuels (The Windscale Inquiry. Report by the Hon. Mr. Justice Parker, 26 January 1978, Vol.1, Report and Annexes 3 to 5, HMSO). Particular attention is given to comments in the report on the ICRP and NRPB, radiation protection standards, and the risks associated with fuel reprocessing. The bases of the judgements made are given, together with Mr. Justice Parker's recommenda-tions for the setting of discharge limits, monitoring discharges and levels of environmental radioactivity, and the assessment of what constitutes a tolerable risk to the public. (U.K)

The Windscale experiment

International Nuclear Information System (INIS)

Blackith, Robert

1984-01-01

The discharge of radioactive waste into the Irish Sea from the Windscale reprocessing plant in Cumbria is discussed from an Irish viewpoint. A history of accidents at the plant is reviewed, and past, present and future levels of discharge to the environment are outlined. The effect on the Irish population of discharges to the marine environment is evaluated by consideration of the food chain and the exposure pathways to man, in particular the concentration of radioactive caesium and plutonium in the flesh of fish in the Irish Sea. The general health effects attributed to radiation exposures are given, and a cluster of Downs Syndrome babies born to mothers who were at the same school in Co. Louth is attributed to increased exposure during the 1957 fire at the Windscale plant. The author concludes that, because of military implications and the need for plutonium for nulcear weapons, the reprocessing plant will continue to operate, but with greatly reduced levels of discharges permitted

The Windscale Inquiry: the public inquiry system on trial

International Nuclear Information System (INIS)

Garry, A.M.

1992-01-01

This thesis is concerned with the Windscale Inquiry of 1977 and its effect on the public inquiry system. It focusses both on the major influences of the Windscale Inquiry process, and on the participants, their aims, motivations, expectations and achievements. It provides the most detailed examination of the Inquiry to date and, as a result, uncovers aspects of the process while have not been explored previously. The central questions of the thesis are: Was the outcome of the Windscale Inquiry inevitable or could it have reached different conclusions? and did the Windscale Inquiry demonstrate that the public inquiry system could be used by a government to reach a decision which it favoured? The thesis argues that the outcome of the Windscale Inquiry was almost inevitable. In fact it was found that the Inspector had made up his mind in favour of oxide reprocessing before the Inquiry opened. However, this finding does not express fully the Inquiry's impact, because, as the thesis shows, the Inquiry became a mechanism which forced the nuclear industry and the government to explain, and substantially alter, some parts of their policies. The process of bringing the government and industry to account, did not alter the THORP decision, but it demonstrated that any subsequent inquiries could subject nuclear developments to searching criticism and investigation. Indeed it is suggested that the Windscale Inquiry made it impossible for subsequent Governments to proceed with nuclear expansion without subjecting them to the public inquiry process. Part I of the thesis examines the history and structure of the public Inquiry system and the relevant aspects of planning law. Part II describes the history of reprocessing and the themes which led to the public inquiry being established. Part III forms the most detailed part of the thesis and examines the Windscale Inquiry process focussing on the participants and the issues involved. (author)

Windscale experiment. A study of Windscale's pollution of the Irish Sea

Energy Technology Data Exchange (ETDEWEB)

Blackith, R

1984-01-01

The discharge of radioactive waste into the Irish Sea from the Windscale reprocessing plant in Cumbria is discussed from an Irish viewpoint. A history of accidents at the plant is reviewed, and past, present and future levels of discharge to the environment are outlined. The effect on the Irish population of discharges to the marine environment is evaluated by consideration of the food chain and the exposure pathways to man, in particular the concentration of radioactive caesium and plutonium in the flesh of fish in the Irish Sea. The general health effects attributed to radiation exposures are given, and a cluster of Downs Syndrome babies born to mothers who were at the same school in Co. Louth is attributed to increased exposure during the 1957 fire at the Windscale plant. The author concludes that, because of military implications and the need for plutonium for nulcear weapons, the reprocessing plant will continue to operate, but with greatly reduced levels of discharges permitted.

Inverse kinetics technique for reactor shutdown measurement: an experimental assessment. [AGR

Energy Technology Data Exchange (ETDEWEB)

Lewis, T. A.; McDonald, D.

1975-09-15

It is proposed to use the Inverse Kinetics Technique to measure the subcritical reactivity as a function of time during the testing of the nitrogen injection systems on AGRs. A description is given of an experimental assessment of the technique by investigating known transients created by control rod movements on a small experimental reactor, (2m high, 1m radius). Spatial effects were observed close to the moving rods but otherwise derived reactivities were independent of detector position and agreed well with the existing calibrations. This prompted the suggestion that data from installed reactor instrumentation could be used to calibrate CAGR control rods.

Comparisons of the emissions in the Windscale and Chernobyl accidents

International Nuclear Information System (INIS)

Chamberlain, A.C.

1987-02-01

The contents are summarized under the following headings: 1) Windscale accident summary 2) Emission of 137 Cs from Windscale 3) Emission of other fission products from Windscale 4) Environmental effects - iodine 5) Environmental effects - caesium. A bibliography is attached and where figures are available, comparisons are made with the Chernobyl fallout, including thyroid iodine burdens for U.K. students who were in Russia at the time of the Chernobyl accident, and milk measurements of Caesium 137 in the U.K. (UK)

Reactor Physics Development for Advanced Gas-Cooled Reactors; Recherches en Physique des Reacteurs, pour des Reacteurs Perfectionnes Refroidis par un Gaz; Razrabotka metodov v oblasti reaktornoj fiziki dlya usovershenstvovannogo reaktora s gazovym okhlazhdeniem; Progresos de la Fisica de los Reactores de Tipo Avanzado Refrigerados por Gas

Energy Technology Data Exchange (ETDEWEB)

Moore, J. [United Kingdom Atomic Energy Authority (United Kingdom)

1964-04-15

The paper is a general one reviewing the detailed experimental and theoretical work that has been done during design, development and commissioning of the Windscale AGR. and in general support of development of Advanced Gas-Cooled Reactors for civil power production. The main purpose of the paper is to describe die considerable amount of work that has been necessary to develop adequate theoretical methods for calculating (a) flux distribution and reactivity balance in a complex reactor core, (b) power distribution in complex fuel geometries, and (c) the effect of irradiation on fuel cycles and power distribution. As an introduction reference is made to experimental information and theoretical methods available from work on uranium Magnox systems and the experimental information obtained from the British Industries Collaborative Experimental Programme (BICEP) both of which provided the starting point for development of theoretical methods applicable to AGRs. The approach to critical facility APEX and the zero energy reactor HERO have been used with regular lattice arrangements and with combinations of perturbers such as control rods in them to determine lattice parameters for AGR and to check the theoretical methods developed for dealing with heterogeneous reactor cores. The theoretical methods that have been developed and used to date are known as hetrecontrol and FTD2. Experiments were designed to check detailed features of these methods and measurements on a number of different sized ''reactor'' cores in APEX and HERO were analysed to determine a self-consistent set of lattice constants that fitted the experimental results. These purely empirical constants were the used in hetrecontrol and FTD2 to successfully plan commissioning and choice of the loading pattern for the Windscale AGR. Reference is made to experimental techniques that have been tested and those developed for the particular problems encountered. The methods examined for measurement of reactivity

Progress in the development of tooling and dismantling methodologies for the Windscale advanced gas cooled reactor (WAGR)

International Nuclear Information System (INIS)

Cross, M.T.; Wareing, M.I.; Dixon, C.

1998-01-01

Decommissioning of the Windscale Advanced Gas-Cooled Reactor (WAGR) is a major UK reactor decommissioning project co-funded by the UK Government, the European Commission and Magnox Electric. WAGR was a CO 2 cooled, graphite moderated reactor which served as a test bed for the development of Advanced Gas-Cooled Reactor technology in the UK. It operated from 1963 until shutdown in 1981. AEA Technology plc are currently the Managing Agents on behalf of UKAEA for the WAGR decommissioning project and are responsible for the co-ordination of the project up to the point when the contents of the reactor core and associated radioactive materials are removed and either disposed of or packaged for disposal at some time in the future. Decommissioning has progressed to the point where the reactor has been dismantled down to the level of the hot gas collection manifold with the removal of the top biological shield, the refuelling standpipes and the top section of the reactor pressure vessel. The 4 heat exchangers have also been removed and committed to shallow land burial. This paper describes the work carried out by AEA Technology under separate contracts of UKAEA in developing some of the equipment and deployment methods for the next phase of active operations required in preparation for the dismantling of the core structure. Most recent work has concentrated on the development of specialist tooling for removal of items of operational waste stored within the reactor core, equipment for cutting and removal of the highly radioactive stainless steel 'loop' pressure tubes, diamond wire cutting equipment for sectioning large diameter pipework, and equipment for dismantling the reactor neutron shield. The paper emphasises the process of adaptation and extension of existing technologies for cost-effective application in the decommissioning environment, the need for adequate forward planning of decommissioning methodologies together with large-scale 'mock-up' testing of equipment to

AGR v PWR

International Nuclear Information System (INIS)

Green, D.

1986-01-01

When the Central Electricity Generating Board (CEGB) invited tenders and placed a contract for the Advanced Gas Cooled Reactor (AGR) at Dungeness B in 1965 -preferring it to the Pressurised Water Reactor (PWR) -the AGR was lamentably ill developed. The effects of the decision were widely felt, for it took the British nuclear industry off the light water reactor highway of world reactor business and up and idiosyncratic private highway of its own, excluding it altogether from any material export business in the two decades which followed. Yet although the UK may have made wrong decisions in rejecting the PWR in 1965, that does not mean that it can necessarily now either correct them, or redeem their consequence, by reversing the choice in 1985. In the 20 years since 1965 the whole world economic and energy picture has been transformed and the national picture with it. Picking up the PWR now could prove as big a disaster as rejecting it may have been in 1965. (author)

What price Windscale

International Nuclear Information System (INIS)

Boyle, S.

1985-11-01

The report examines the economic and waste management arguments used to justify the reprocessing of spent nuclear fuel. With specific reference to Windscale reprocessing plant, it concludes that reprocessing is not the optimum approach to the management of spent fuel for the next decade or longer, and that the alternatives of long-term storage and/or direct disposal are more economic and more environmentally sound alternatives. (author)

Reactor decommissioning

International Nuclear Information System (INIS)

Lawton, H.

1984-01-01

A pioneering project on the decommissioning of the Windscale Advanced Gas-cooled Reactor, by the UKAEA, is described. Reactor data; policy; waste management; remote handling equipment; development; and recording and timescales, are all briefly discussed. (U.K.)

Windscale inquiry

International Nuclear Information System (INIS)

Lambert, C.M.

1981-01-01

The nuclear debate, far from being concluded by the Windscale decision, was in fact opened up and its scope widened to take into account the political, international, environmental and social issues involved. This debate continues and the selection of literature presented here aims to illustrate all aspects of the Inquiry and its implications. The material is presented in two main sections. Section A is concerned with the Inquiry itself: the proceedings, the report and the government's decision. Section B presents a selection of the literature and debate that resulted. (author)

A comparison of predicted and measured graphite moderator behaviour during 16 years' operation of the Windscale advanced gas-cooled reactor

International Nuclear Information System (INIS)

Prince, N.

1980-01-01

The Windscale AGR has operated since January 1963 at a cumulative load factor of nearly 70% during which time the peak irradiation damage dose has built up to more than 5x10 n/cm 2 (equivalent DIDO nickel), well beyond its original design life. This paper recounts the findings of monitoring measurements on the moderator at high exposure levels with regard to radiolytic oxidation and various aspects of dimensional change behaviour. It is shown that the measured dimensional changes are in good agreement with predictions based on small specimens irradiated in MTR's, thus confirming the absence of any size effect and adding confidence to predictive methods. However, recent measurements of channel straightness show that the observed distortions are only about 10% of the maximum predictions, perhaps due to localised creep at the brick ends creating flats which impart some stability to the columns of moderator bricks. The magnitude of radiolytic oxidation determined by trepanning specimens from the core in 1976 was found to be only about 5%, whereas it was thought possible that peak weight losses would conceivably be as high as 11% due to the depleted concentration of methane inhibitor reaching the brick interior by diffusion processes. It has subsequently been shown by calculation that this result is consistent with the existence of radial pressure drops across the moderator brick walls giving greater penetration of methane inhibitor. (author)

Penney's Windscale thoughts

Energy Technology Data Exchange (ETDEWEB)

Pearce, F

1988-01-07

The paper concerns the official file on the nuclear fire at Windscale in October 1957, which was written by Sir William Penney. The file was based on a 10-day investigation, and describes the physical causes and consequences of the fire. The events of the accident are described, along with the political events of the time concerning the U.S.A. and nuclear weapons, attempts to put out the fire, iodine fall-out in the milk, and polonium 210 contamination.

AGR-2 Data Qualification Interim Report

International Nuclear Information System (INIS)

Abbott, Michael L.

2010-01-01

Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

AGR-2 Data Qualification Interim Report

Energy Technology Data Exchange (ETDEWEB)

Michael L. Abbott

2010-09-01

Projects for the very high temperature reactor (VHTR) Technology Development Office program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program established the NGNP Data Management and Analysis System (NDMAS) to manage and document VHTR data qualification, for storage of the data in a readily accessible electronic form, and to assist in the analysis and presentation of the data. This document gives the status of NDMAS processing and qualification of data associated with the initial reactor cycle (147A) of the second Advanced Gas Reactor (AGR-2) experiment which began on June 21, 2010. Because it is early in the AGR-2 experiment, data from only two AGR-2 data streams are reported on: Fuel Fabrication and Fuel Irradiation data. As of August 1, 2010, approximately 311,000 irradiation data records have been stored in NDMAS, and qualification tests are in progress. Preliminary information indicates that TC 2 in Capsule 2 failed prior to start of the experiment, and NDMAS testing has thus far identified only two invalid data values from the METSO data collection system Data from the Fission Product Monitoring System (FPMS) are not currently processed until after reactor cycle shutdown and have not yet been received. A description of the ATR operating conditions data associated with the AGR-2 experiment (e.g., power levels) are summarized in the AGR-1 data qualification report (INL/EXT-09-16460). Since ATR data are collected under ATR program data quality requirements (i.e., outside the VHTR program), the NGNP program and NDMAS do not take additional actions to qualify these data other than NDMAS capture testing. Data qualification of graphite characterization data collected under the Graphite Technology Development Project is reported in a separate status report (Hull 2010).

AGR-1 Thermocouple Data Analysis

International Nuclear Information System (INIS)

Einerson, Jeff

2012-01-01

This report documents an effort to analyze measured and simulated data obtained in the Advanced Gas Reactor (AGR) fuel irradiation test program conducted in the INL's Advanced Test Reactor (ATR) to support the Next Generation Nuclear Plant (NGNP) R and D program. The work follows up on a previous study (Pham and Einerson, 2010), in which statistical analysis methods were applied for AGR-1 thermocouple data qualification. The present work exercises the idea that, while recognizing uncertainties inherent in physics and thermal simulations of the AGR-1 test, results of the numerical simulations can be used in combination with the statistical analysis methods to further improve qualification of measured data. Additionally, the combined analysis of measured and simulation data can generate insights about simulation model uncertainty that can be useful for model improvement. This report also describes an experimental control procedure to maintain fuel target temperature in the future AGR tests using regression relationships that include simulation results. The report is organized into four chapters. Chapter 1 introduces the AGR Fuel Development and Qualification program, AGR-1 test configuration and test procedure, overview of AGR-1 measured data, and overview of physics and thermal simulation, including modeling assumptions and uncertainties. A brief summary of statistical analysis methods developed in (Pham and Einerson 2010) for AGR-1 measured data qualification within NGNP Data Management and Analysis System (NDMAS) is also included for completeness. Chapters 2-3 describe and discuss cases, in which the combined use of experimental and simulation data is realized. A set of issues associated with measurement and modeling uncertainties resulted from the combined analysis are identified. This includes demonstration that such a combined analysis led to important insights for reducing uncertainty in presentation of AGR-1 measured data (Chapter 2) and interpretation of

AGR-1 Thermocouple Data Analysis

Energy Technology Data Exchange (ETDEWEB)

Jeff Einerson

2012-05-01

This report documents an effort to analyze measured and simulated data obtained in the Advanced Gas Reactor (AGR) fuel irradiation test program conducted in the INL's Advanced Test Reactor (ATR) to support the Next Generation Nuclear Plant (NGNP) R&D program. The work follows up on a previous study (Pham and Einerson, 2010), in which statistical analysis methods were applied for AGR-1 thermocouple data qualification. The present work exercises the idea that, while recognizing uncertainties inherent in physics and thermal simulations of the AGR-1 test, results of the numerical simulations can be used in combination with the statistical analysis methods to further improve qualification of measured data. Additionally, the combined analysis of measured and simulation data can generate insights about simulation model uncertainty that can be useful for model improvement. This report also describes an experimental control procedure to maintain fuel target temperature in the future AGR tests using regression relationships that include simulation results. The report is organized into four chapters. Chapter 1 introduces the AGR Fuel Development and Qualification program, AGR-1 test configuration and test procedure, overview of AGR-1 measured data, and overview of physics and thermal simulation, including modeling assumptions and uncertainties. A brief summary of statistical analysis methods developed in (Pham and Einerson 2010) for AGR-1 measured data qualification within NGNP Data Management and Analysis System (NDMAS) is also included for completeness. Chapters 2-3 describe and discuss cases, in which the combined use of experimental and simulation data is realized. A set of issues associated with measurement and modeling uncertainties resulted from the combined analysis are identified. This includes demonstration that such a combined analysis led to important insights for reducing uncertainty in presentation of AGR-1 measured data (Chapter 2) and interpretation of

Windscale Report: a nuclear apologia

International Nuclear Information System (INIS)

Patterson, W.C.

1978-01-01

Government representatives have pointed repeatedly with pride to Britain's longest nuclear planning inquiry, The Windscale Inquiry, as a model of open examination of a sensitive nuclear proposal. The official Report of the Windscale Inquiry, published in March 1978, bears little relationship to the proceedings of the Inquiry, according to the author. Instead, the Report is a heavy-handed nuclear apologia, he says, so clumsily one-sided as to provoke unease even among many Britons previously unmoved by the issue which gave rise to the inquiry. Windscale, built following WW II to produce plutonium for Britain's nuclear weapons, is now operated by British Nuclear Fuels Ltd. In 1973, BNFL began to plan construction of a new full-scale oxide-fuel reprocessing plant. Protests delayed construction until the inquiry was planned and the inquiry team was formulated in March 1977. When the Inquiry ended, the inspector closeted himself to write the Report. The Report recommended that the oxide fuel reprocessing plant be built immediately. BNFL had asserted that the proposed thermal oxide reprocessing plant, THORP, was necessary for the management of spent fuel from British and other nuclear plants; that it was desirable for ''energy conservation,'' by recovering uranium and plutonium for re-use; that radioactive emissions within and outside the plant would pose no hazard; and that the servicing of foreign customers would not increase the risk of proliferation of nuclear weapons, but would rather help to persuade other countries not to reprocess their own fuel. The inspector agreed without qualification and with emphasis. In doing so he made no attempt even to describe the detailed evidence on either side, or to discuss the cases advanced by objectors. The author discusses the principal conclusions of the report and cites its futility

AGR-2 Irradiation Test Final As-Run Report

Energy Technology Data Exchange (ETDEWEB)

Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States). VHTR Program

2014-08-01

This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technology Development Office (TDO) program. The objectives of the AGR-2 experiment are to: 1. Irradiate UCO (uranium oxycarbide) and UO₂ (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. 2. Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. 3. Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO₂ TRISO (tristructural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO₂ particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S.-produced fuel.

AGR-2 Irradiation Test Final As-Run Report

Energy Technology Data Exchange (ETDEWEB)

Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States). VHTR Program

2014-08-01

This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO₂ (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO₂ TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO₂ particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel.

Windscale: a case history in the political art of muddling through

International Nuclear Information System (INIS)

Wynne, B.

1980-01-01

This chapter concentrates mainly upon those factors which preceded and eventually led to the Windscale Inquiry (into the BNFL proposal to construct a plant to reprocess spent nuclear fuel from reactors using oxide fuels). This will help to illustrate some of the many covert themes which permeated the Inquiry as an exercise in conflict-management, and hopefully should assist in the understanding of the limitations of this form of decision-making process. The chapter will conclude with a comment upon the role of the Inquiry in the wider political context of the British energy 'debate' and upon the likely implications of the Inquiry for future decision-making ventures on similar technological developments. (author)

Windscale pile core surveys

International Nuclear Information System (INIS)

Curtis, R.F.; Mathews, R.F.

1996-01-01

The two Windscale Piles were closed down, defueled as far as possible and mothballed for thirty years following a fire in the core of Pile 1 in 1957 resulting from the spontaneous release of stored Wigner energy in the graphite moderator. Decommissioning of the reactors commenced in 1987 and has reached the stage where the condition of both cores needs to be determined. To this end, non-intrusive and intrusive surveys and sampling of the cores have been planned and partly implemented. The objectives for each Pile differ slightly. The location and quantity of fuel remaining in the damaged core of Pile 1 needed to be established, whereas the removal of all fuel from Pile 2 needed to be confirmed. In Pile 1, the possible existence of a void in the core is to be explored and in Pile 2, the level of Wigner energy remaining required to be quantified. Levels of radioactivity in both cores needed to be measured. The planning of the surveys is described including strategy, design, safety case preparation and the remote handling and viewing equipment required to carry out the inspection, sampling and monitoring work. The results from the completed non-intrusive survey of Pile 2 are summarised. They confirm that the core is empty and the graphite is in good condition. The survey of Pile 1 has just started. (UK)

PIE on Safety-Tested AGR-1 Compact 5-1-1

Energy Technology Data Exchange (ETDEWEB)

Hunn, John D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Morris, Robert Noel [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Baldwin, Charles A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Montgomery, Fred C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gerczak, Tyler J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-08-01

Post-irradiation examination (PIE) is being performed in support of tristructural isotropic (TRISO) coated particle fuel development and qualification for High-Temperature Gas-cooled Reactors (HTGRs). AGR-1 was the first in a series of TRISO fuel irradiation experiments initiated in 2006 under the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program; this work continues to be funded by the Department of Energy's Office of Nuclear Energy as part of the Advanced Reactor Technologies (ART) initiative. AGR-1 fuel compacts were fabricated at Oak Ridge National Laboratory (ORNL) in 2006 and irradiated for three years in the Idaho National Laboratory (INL) Advanced Test Reactor (ATR) to demonstrate and evaluate fuel performance under HTGR irradiation conditions. PIE is being performed at INL and ORNL to study how the fuel behaved during irradiation, and to examine fuel performance during exposure to elevated temperatures at or above temperatures that could occur during a depressurized conduction cooldown event. This report summarizes safety testing of irradiated AGR-1 Compact 5-1-1 in the ORNL Core Conduction Cooldown Test Facility (CCCTF) and post-safety testing PIE.

AGR-1 Data Qualification Report

International Nuclear Information System (INIS)

Abbott, Michael

2010-01-01

Projects for the very high temperature reactor (VHTR) Technology Development Office (TDO) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor experiment (AGR-1), the processing of these data within NDMAS, and reports the qualification status of the data. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category assigned by the data generator. They include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent quality assurance program. The NDMAS database processing and qualification status of the following five data streams is reported in this document: (1) Fuel fabrication data. All data have been processed into the NDMAS database and qualified (1,819 records). (2) Fuel irradiation data. Data from all 13 AGR-1 reactor cycles have been processed into the NDMAS database and tested. Of these, 85% have been qualified and 15% have failed NDMAS accuracy testing. (3) FPMS data. Reprocessed (January 2010) data from all 13 AGR-1 reactor cycles have been processed into the database and capture tested. Final qualification of these data will be recorded after QA approval of an Engineering Calculations and Analysis Report currently

Progress with the AGR system

International Nuclear Information System (INIS)

Merrett, D.J.

1984-01-01

The AGR programme was initiated in 1965 with the ordering of the Dungeness 'B' reactor, followed by Hinkley point 'B' (1965), Hunterston 'B' (1968), Hartlepool (1970), Heysham I (1970) and the two latest stations at Heysham II and Torness. The paper reviews the achievements and prospects for the AGR system under 6 topic headings. These include: operational experience at Hinkley Point 'B' and Hunterston'B', commissioning of Dungeness 'B', Hartlepool and Heysham I, Heysham II/Torness design, Heysham II/Torness programme and finally future prospects. (U.K.)

Review of CAGR fuel performance

Energy Technology Data Exchange (ETDEWEB)

Boocock, P.M. (South of Scotland Electricity Board, Glasgow (UK)); Eldred, V.W. (UKAEA Windscale Nuclear Power Development Labs.); Hines, G.F. (UKAEA Atomic Energy Establishment, Winfrith); Seeley, T.A. (British Nuclear Fuels Ltd., Springfields); Shaw, R.A. (UKAEA Springfields Nuclear Power Development Labs.); Waddington, J.S. (Central Electricity Generating Board, Berkeley (UK). Berkeley Nuclear Labs.)

1983-04-01

The performance of CAGR fuel in the Electricity Board's reactors is reviewed in the light of operating experience and the post-irradiation examination assessments which have been carried out. The results show that the extrapolation of the design from the Windscale AGR prototype has been very successful. Future trends in fuel design in order to achieve the higher burn-up targets now being specified are discussed.

AGR core models and their application to HTRs and RBMKs

International Nuclear Information System (INIS)

Baylis, Samuel

2014-01-01

EDF Energy operates 14 AGRs, commissioned between 1976 and 1989. The graphite moderators of these gas cooled reactors are subjected to a number of ageing processes under fast neutron irradiation in a high temperature CO2 environment. As the graphite ages, continued safe operation requires an advanced whole-core modeling capability to enable accurate assessments of the core’s ability to fulfil fundamental nuclear safety requirements. This is also essential in evaluating the reactor's remaining economic lifetime, and similar assessments are useful for HTRs in the design stage. A number of computational and physical models of AGR graphite cores have been developed or are in development, allowing simulation of the reactors in normal, fault and seismic conditions. Many of the techniques developed are applicable to other graphite moderated reactors. Modeling of the RBMK allows validation against a core in a more advanced state of ageing than the AGRs, while there is also an opportunity to adapt the models for high temperature reactors. As an example, a finite element model of the HTR-PM side reflector based on rigid bodies and nonlinear springs is developed, allowing rapid assessments of distortion in the structure to be made. A model of the RBMK moderator has also been produced using an established AGR code based on similar methods. In addition, this paper discusses the limitations of these techniques and the development of more complex core models that address these limitations, along with the lessons that can be applied to HTRs. (author)

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

International Nuclear Information System (INIS)

Standring, P.N.

1999-01-01

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

Scottish Nuclear Limited: the AGR - past, present and future

International Nuclear Information System (INIS)

Anderson, D.; Barnes, G.G.

1993-01-01

This article reviews the historical development of the AGR (advanced gas-cooled reactor) in Scotland from its inception to its current successfully established position. It examines where the AGRs will go in the future and concludes with the strategic role of the existing and new plant in the market-led electricity supply industry. (Author)

Improving the AGR fuel testing power density profile versus irradiation-time in the advanced test reactor

International Nuclear Information System (INIS)

Chang, Gray S.; Lillo, Misti A.; Maki, John T.; Petti, David A.

2009-01-01

The Very High Temperature gas-cooled Reactor (VHTR), which is currently being developed, achieves simplification of safety through reliance on ceramic-coated fuel particles. Each TRISO-coated fuel particle has its own containment which serves as the principal barrier against radionuclide release under normal operating and accident conditions. These fuel particles, in the form of graphite fuel compacts, are currently undergoing a series of irradiation tests in the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) to support the Advanced Gas-Cooled Reactor (AGR) fuel qualification program. A representive coated fuel particle with an 235 U enrichment of 19.8 wt% was used in this analysis. The fuel burnup analysis tool used to perform the neutronics study reported herein, couples the Monte Carlo transport code MCNP, with the radioactive decay and burnup code ORIGEN2. The fuel burnup methodology known as Monte-Carlo with ORIGEN2 (MCWO) was used to evaluate the AGR experiment assembly and demonstrate compliance with ATR safety requirements. For the AGR graphite fuel compacts, the MCWO-calculated fission power density (FPD) due to neutron fission in 235 U is an important design parameter. One of the more important AGR fuel testing requirements is to maintain the peak fuel compact temperature close to 1250degC throughout the proposed irradiation campaign of 550 effective full power days (EFPDs). Based on the MCWO-calculated FPD, a fixed gas gap size was designed to allow regulation of the fuel compact temperatures throughout the entire fuel irradiation campaign by filling the gap with a mixture of helium and neon gases. The chosen fixed gas gap can only regulate the peak fuel compact temperature in the desired range during the irradiation test if the ratio of the peak power density to the time-dependent low power density (P/T) at 550 EFPDs is less than 2.5. However, given the near constant neutron flux within the ATR driver core and the depletion of 235 U

Mod increases AGR boiler output

International Nuclear Information System (INIS)

Jones, W.K.C.; Rider, G.; Taylor, D.E.

1986-01-01

During the commissioning runs of the first reactor units at Heysham I and Hartlepool Advanced Gas-cooled Reactors (AGRs), non-uniform temperature distributions were observed across individual boiler units which were more severe than those predicted from the design analysis. This article describes the re-orificing (referruling) of the boilers to overcome this problem. The referruling has reduced boiler sensitivity and resulted in an increase of load of 7 or 8%. (U.K.)

AGR-1 Data Qualification Interim Report

International Nuclear Information System (INIS)

Abbott, Machael

2009-01-01

Projects for the very-high-temperature reactor (VHTR) program provide data in support of Nuclear Regulatory Commission licensing of the VHTR. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high temperature and high fluence environments. The VHTR Program has established the NGNP Data Management and Analysis System (NDMAS) to ensure that VHTR data are (1) qualified for use, (2) stored in a readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the first NDMAS objective. It describes the data streams associated with the first Advanced Gas Reactor (AGR-1) experiment, the processing of these data within NDMAS, and reports the interim FY09 qualification status of the AGR-1 data to date. Data qualification activities within NDMAS for specific types of data are determined by the data qualification category, which is assigned by the data generator, and include: (1) capture testing, to confirm that the data stored within NDMAS are identical to the raw data supplied, (2) accuracy testing, to confirm that the data are an accurate representation of the system or object being measured, and (3) documentation that the data were collected under an NQA-1 or equivalent QA program. The interim qualification status of the following four data streams is reported in this document: (1) fuel fabrication data, (2) fuel irradiation data, (3) fission product monitoring system (FPMS) data, and (4) Advanced Test Reactor (ATR) operating conditions data. A final report giving the NDMAS qualification status of all AGR-1 data (including cycle 145A) is planned for February 2010

Safety Testing of AGR-2 UCO Compacts 6-4-2 and 2-3-1

Energy Technology Data Exchange (ETDEWEB)

Hunn, John D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Morris, Robert N. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Baldwin, Charles A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Burns, Zachary M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Montgomery, Fred C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Skitt, Darren J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-08-01

Post-irradiation examination (PIE) and elevated-temperature safety testing are being performed on tristructural-isotropic (TRISO) coated-particle fuel compacts from the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program second irradiation experiment (AGR-2). Details on this irradiation experiment have been previously reported [Collin 2014]. The AGR-2 PIE effort builds upon the understanding acquired throughout the AGR-1 PIE campaign [Demkowicz et al. 2015] and is establishing a database for the different AGR-2 fuel designs.

Technical assessment of the significance of Wigner energy for disposal of graphite wastes from the Windscale Piles

International Nuclear Information System (INIS)

Guppy, R.M.; Wisbey, S.J.; McCarthy, J.

2001-01-01

Plans to dismantle the core of the Windscale Pile 1 reactor, and to package the waste for interim storage and eventual disposal, are well advanced. UK Nirex Limited, currently responsible for identifying and developing a site primarily for disposal of the wide range of intermediate level wastes, is addressing the suitability of the waste from Windscale Pile 1, for transport to, and disposal at, a deep waste repository. To support the decommissioning of Windscale Pile 1, information on the condition of the graphite has been sought. Despite the fire in 1957, recent sampling of regions of the core has shown that much of the graphite still contains significant residual Wigner energy. Unless it can be shown that Wigner energy will not be released at a significant rate during operations such as waste packaging or handling of the package, or after disposal, future safety cases may be undermined. A model for the release of Wigner energy has been developed, which describes the stored energy as a set of defects with different activation energies. Initial values of stored energy are attributed to each member of the set, and the energy is released using first order decay processes. By appropriate selection of the range of activation energies and stored energies attributable to each population of defects, experimentally determined releases of stored energy as a function of temperature can be reproduced by the model. Within the disposal environment, the packages will be subject to modest heating from external sources, including the host rocks, radioactive decay, corrosion processes and heat from curing of backfill materials in the disposal vaults. The Wigner energy release model has been used in combination with finite element thermal modelling to assess the temperature evolution of stacks of waste packages located within hypothetical disposal vaults. It has also been used to assess the response of individual waste packages exposed to fires. This paper provides a summary of the

Uncertainty Quantification of Calculated Temperatures for the AGR 3/4 Experiment

International Nuclear Information System (INIS)

Pham, Binh Thi-Cam

2015-01-01

A series of Advanced Gas Reactor (AGR) irradiation experiments are being conducted within the Advanced Reactor Technology (ART) Fuel Development and Qualification Program. The main objectives of the fuel experimental campaign are to provide the necessary data on fuel performance to support fuel process development, qualify a fuel design and fabrication process for normal operation and accident conditions, and support development and validation of fuel performance and fission product transport models and codes (PLN 3636, 'Technical Program Plan for INL Advanced Reactor Technologies Technology Development Office/Advanced Gas Reactor Fuel Development and Qualification Program'). The AGR 3/4 test was inserted in the Northeast Flux Trap position in the Advanced Test Reactor (ATR) core at Idaho National Laboratory (INL) in December 2011 and successfully completed irradiation in mid-April 2014, resulting in irradiation of the tristructural isotropic (TRISO) fuel for 369.1 effective full-power days (EFPDs) during approximately 2.4 calendar years. The AGR 3/4 data, including the irradiation data and calculated results, were qualified and stored in the Nuclear Data Management and Analysis System (NDMAS). To support the U.S. TRISO fuel performance assessment and to provide data for validation of fuel performance and fission product transport models and codes, the daily as run thermal analysis has been performed separately on each of twelve AGR 3/4 capsules for the entire irradiation as discussed in ECAR-2807, 'AGR 3/4 Daily As Run Thermal Analyses'. The ABAQUS code's finite element-based thermal model predicts the daily average volume average (VA) fuel temperature (FT), peak FT, and graphite matrix, sleeve, and sink temperature in each capsule. The JMOCUP simulation codes were also created to perform depletion calculations for the AGR 3/4 experiment (ECAR-2753, 'JMOCUP As-Run Daily Physics Depletion Calculation for the AGR 3/4 TRISO Particle

Uncertainty Quantification of Calculated Temperatures for the AGR 3/4 Experiment

Energy Technology Data Exchange (ETDEWEB)

Pham, Binh Thi-Cam [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-09-01

A series of Advanced Gas Reactor (AGR) irradiation experiments are being conducted within the Advanced Reactor Technology (ART) Fuel Development and Qualification Program. The main objectives of the fuel experimental campaign are to provide the necessary data on fuel performance to support fuel process development, qualify a fuel design and fabrication process for normal operation and accident conditions, and support development and validation of fuel performance and fission product transport models and codes (PLN 3636, “Technical Program Plan for INL Advanced Reactor Technologies Technology Development Office/Advanced Gas Reactor Fuel Development and Qualification Program”). The AGR 3/4 test was inserted in the Northeast Flux Trap position in the Advanced Test Reactor (ATR) core at Idaho National Laboratory (INL) in December 2011 and successfully completed irradiation in mid-April 2014, resulting in irradiation of the tristructural isotropic (TRISO) fuel for 369.1 effective full-power days (EFPDs) during approximately 2.4 calendar years. The AGR 3/4 data, including the irradiation data and calculated results, were qualified and stored in the Nuclear Data Management and Analysis System (NDMAS). To support the U.S. TRISO fuel performance assessment and to provide data for validation of fuel performance and fission product transport models and codes, the daily as run thermal analysis has been performed separately on each of twelve AGR 3/4 capsules for the entire irradiation as discussed in ECAR-2807, “AGR 3/4 Daily As Run Thermal Analyses”. The ABAQUS code’s finite element-based thermal model predicts the daily average volume average (VA) fuel temperature (FT), peak FT, and graphite matrix, sleeve, and sink temperature in each capsule. The JMOCUP simulation codes were also created to perform depletion calculations for the AGR 3/4 experiment (ECAR-2753, “JMOCUP As-Run Daily Physics Depletion Calculation for the AGR 3/4 TRISO Particle Experiment in ATR

How safe is an AGR

International Nuclear Information System (INIS)

Wilkinson, Max

1987-01-01

The paper concerns the safety of an AGR, in the light of the Chernobyl and Three Mile Island reactor accidents. To assess the safety systems the resources editor of the Financial Times newspaper spent an afternoon trying to do as much damage as possible to one of the Hinkley Point B advanced gas cooled reactors - on the simulator at the Central Electricity Generating Board's training centre at Oldbury. An account of the experience in the nuclear power control room is given. (U.K.)

Taming Windscale's piles

International Nuclear Information System (INIS)

Adams, A.L.

1989-01-01

The options as to what to do with the Windscale Piles are being assessed before a final decision on decommissioning is made. Both Piles were shutdown in 1957 following the fire in the Pile number 1. Pile 1 still contains 22 tons of natural uranium fuel. The details of graphite moderator content, biological shielding and other components and containment are given. The fuel and isotope channels in Pile 2 have been examined and the air and water ducts have been inspected. The chimneys of both Piles are contaminated and all entrances have been sealed. Before any work starts the air outlet ducts will be sealed from the chimney and a ventilation system installed. A manipulator is being prepared to remove the remaining fuel elements from both Piles. The proposed decommissioning programme for both Piles is outlined. (U.K.)

AGR-2 Data Qualification Report for ATR Cycles 147A, 148A, 148B, and 149A

International Nuclear Information System (INIS)

Abbott, Michael L.; Daum, Keith A.

2011-01-01

This report presents the data qualification status of fuel irradiation data from the first four reactor cycles (147A, 148A, 148B, and 149A) of the on-going second Advanced Gas Reactor (AGR-2) experiment as recorded in the NGNP Data Management and Analysis System (NDMAS). This includes data received by NDMAS from the period June 22, 2010 through May 21, 2011. AGR-2 is the second in a series of eight planned irradiation experiments for the AGR Fuel Development and Qualification Program, which supports development of the very high temperature gas-cooled reactor (VHTR) under the Next Generation Nuclear Plant (NGNP) Project. Irradiation of the AGR-2 test train is being performed at the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) and is planned for 600 effective full power days (approximately 2.75 calendar years) (PLN-3798). The experiment is intended to demonstrate the performance of UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Data qualification status of the AGR-1 experiment was reported in INL/EXT-10-17943 (Abbott et al. 2010).

AGR-2 Data Qualification Report for ATR Cycles 147A, 148A, 148B, and 149A

Energy Technology Data Exchange (ETDEWEB)

Michael L. Abbott; Keith A. Daum

2011-08-01

This report presents the data qualification status of fuel irradiation data from the first four reactor cycles (147A, 148A, 148B, and 149A) of the on-going second Advanced Gas Reactor (AGR-2) experiment as recorded in the NGNP Data Management and Analysis System (NDMAS). This includes data received by NDMAS from the period June 22, 2010 through May 21, 2011. AGR-2 is the second in a series of eight planned irradiation experiments for the AGR Fuel Development and Qualification Program, which supports development of the very high temperature gas-cooled reactor (VHTR) under the Next Generation Nuclear Plant (NGNP) Project. Irradiation of the AGR-2 test train is being performed at the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) and is planned for 600 effective full power days (approximately 2.75 calendar years) (PLN-3798). The experiment is intended to demonstrate the performance of UCO (uranium oxycarbide) and UO2 (uranium dioxide) fuel produced in a large coater. Data qualification status of the AGR-1 experiment was reported in INL/EXT-10-17943 (Abbott et al. 2010).

Safety testing of AGR-2 UO₂ compacts 3-3-2 and 3-4-2

Energy Technology Data Exchange (ETDEWEB)

Hunn, John D. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Morris, Robert Noel [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Baldwin, Charles A. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Montgomery, Fred C. [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

2015-09-01

Post-irradiation examination (PIE) is in progress on tristructural-isotropic (TRISO) coated-particle fuel compacts from the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program second irradiation experiment (AGR-2) [Collin 2014]. The AGR-2 PIE will build upon new information and understanding acquired throughout the recently-concluded six-year AGR-1 PIE campaign [Demkowicz et al. 2015] and establish a database for the different AGR-2 fuel designs.

Windscale: a case study in public scrutiny

International Nuclear Information System (INIS)

Bugler, J.

1978-01-01

An account is given of the action in Parliament - and relevant action outside Parliament - leading to the setting up of a public inquiry into the application by British Nuclear Fuels Limited for planning permission to construct a thermal oxide reprocessing plant at their Windscale works. The hearings and the subsequent report by the inspector are also examined from the points of view of public involvement and parliamentary and government machinery. (U.K.)

A Survey of the Fuel Cycles Operated in the United Kingdom; Etude d'ensemble sur les cycles de combustible au Royaume-Uni; Obzor toplivnykh tsiklov, ispol'zuemykh v soedinennom korolevstve; Estudio de los ciclos de combustible utilizados en el Reino Unido

Energy Technology Data Exchange (ETDEWEB)

Allday, C. [United Kingdom Atomic Energy Authority, Risley, Warrington, Lancs (United Kingdom)

1963-10-15

(a) The natural uranium/ magnox fuel cycle. The United Kingdom have chosen the natural uranium graphite-moderated gas-cooled reactor as the basis of their nuclear power programme. They have operated the reactors at Calder Hall and Chapelcross for seven years; the Berkeley and Bradwell reactors of the CEGB are now operating, and reactors at seven other sites are under construction or planned. The fuel for these reactors is designed and manufactured at the U.K.A.E.A. Springfields factory and then transported to the reactor site for loading. After irradiation and discharge the fuel is transported to the U.K.A.E.A. site at Windscale for separation of uranium and plutonium from fission products. The paper outlines the UK experience of design and manufacture of fuel, re actor operation, transport of irradiated fuel and subsequent processing of the fuel. Mention is made of the behaviour of fuel in a reactor and alternative charging and discharging programmes, the subject is further elaborated in another paper. (b) Reactors using enriched fuels. The UK are developing an advanced gas-cooled reactor (AGR), the prototype reactor of which came on power in 1963. The fuel is manufactured from enriched uranium oxide canned in stainless steel and it will be reprocessed through a ''head-end'' which will be added to the Windscale Magnox separation plant. The enriched uranium for the AGR is produced in the UK Diffusion Plant at Capenhurst. An alternative to enriched uranium oxide as a fuel is plutonium-enriched natural-uranium oxide. The paper outlines the experience in production of oxide fuel for AGR, the operating experience with the reactor so far and the plans for reprocessing the fuel. The alternative use of a plutonium fuel is considered and the effects of this on costs and the fuel cycle. Finally the paper outlines the place of Magnox and AGR reactors in the UK power programme. (author) [French] a) Cycle de l'uranlum naturel gaine de magnox. Le Royaume-Uni a choisi de fonder

The Windscale Advanced Gas Cooled Reactor (WAGR) Decommissioning Project A Close Out Report for WAGR Decommissioning Campaigns 1 to 10 - 12474

Energy Technology Data Exchange (ETDEWEB)

Halliwell, Chris [Sellafield Ltd, Sellafield (United Kingdom)

2012-07-01

The reactor core of the Windscale Advanced Gas-Cooled Reactor (WAGR) has been dismantled as part of an ongoing decommissioning project. The WAGR operated until 1981 as a development reactor for the British Commercial Advanced Gas cooled Reactor (CAGR) power programme. Decommissioning began in 1982 with the removal of fuel from the reactor core which was completed in 1983. Subsequently, a significant amount of engineering work was carried out, including removal of equipment external to the reactor and initial manual dismantling operations at the top of the reactor, in preparation for the removal of the reactor core itself. Modification of the facility structure and construction of the waste packaging plant served to provide a waste route for the reactor components. The reactor core was dismantled on a 'top-down' basis in a series of 'campaigns' related to discrete reactor components. This report describes the facility, the modifications undertaken to facilitate its decommissioning and the strategies employed to recognise the successful decommissioning of the reactor. Early decommissioning tasks at the top of the reactor were undertaken manually but the main of the decommissioning tasks were carried remotely, with deployment systems comprising of little more than crane like devices, intelligently interfaced into the existing structure. The tooling deployed from the 3 tonne capacity (3te) hoist consisted either purely mechanical devices or those being electrically controlled from a 'push-button' panel positioned at the operator control stations, there was no degree of autonomy in the 3te hoist or any of the tools deployed from it. Whilst the ATC was able to provide some tele-robotic capabilities these were very limited and required a good degree of driver input which due to the operating philosophy at WAGR was not utilised. The WAGR box proved a successful waste package, adaptable through the use of waste box furniture specific to the

AGR-2 irradiation test final as-run report, Rev. 1

International Nuclear Information System (INIS)

2014-01-01

This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO 2 (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities; (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing; and, (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO 2 TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO 2 particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel. In order to achieve the test objectives, the AGR-2 experiment was irradiated in the B-12 position of the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for a total irradiation duration of 559.2 effective full power days (EFPD). Irradiation began on June 22, 2010, and ended on October 16, 2013, spanning 12 ATR power cycles and approximately three and a half calendar years. The

AGR-2 Irradiation Test Final As-Run Report, Rev 2

Energy Technology Data Exchange (ETDEWEB)

Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2014-08-01

This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technical Development Office (TDO) program. The objectives of the AGR-2 experiment are to: (a) Irradiate UCO (uranium oxycarbide) and UO₂ (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. (b) Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. (c) Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO₂ TRISO (tri-structural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO₂ particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S. produced fuel. In order to achieve the test objectives, the AGR-2 experiment was irradiated in the B-12 position of the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for a total irradiation duration of 559.2 effective full power days (EFPD). Irradiation began on June 22, 2010, and ended on October 16, 2013, spanning 12 ATR power cycles and approximately three and a

Reactor accidents and the actions of fire brigades. Plea for nuclear phaseout. An analytic report on Leipzig, Windscale, Chernobyl and Fukushima; Reaktorunfaelle und die Handlungen der Feuerwehr. Plaedoyer fuer den Atomausstieg. Ein Analysebericht zu Leipzig, Windscale, Tschernobyl und Fukushima

Energy Technology Data Exchange (ETDEWEB)

Steffler, Reinhard

2016-11-01

The report covers the historically first fire brigade action at the ''uranium machine'' on June 23th 1942 in Leipzig, and the fire brigade actions in Windscale (October 11, 1957), Chernobyl and Fukushima Daiichi. Further issues are the behavior of the media, selected features of the fire brigade actions, and a discussion of questions concerning the preparedness of the fire brigades.

AGR core safety assessment methodologies

International Nuclear Information System (INIS)

McLachlan, N.; Reed, J.; Metcalfe, M.P.

1996-01-01

To demonstrate the safety of its gas-cooled graphite-moderated AGR reactors, nuclear safety assessments of the cores are based upon a methodology which demonstrates no component failures, geometrical stability of the structure and material properties bounded by a database. All AGRs continue to meet these three criteria. However, predictions of future core behaviour indicate that the safety case methodology will eventually need to be modified to deal with new phenomena. A new approach to the safety assessment of the cores is currently under development, which can take account of these factors while at the same time providing the same level of protection for the cores. This approach will be based on the functionality of the core: unhindered movement of control rods, continued adequate cooling of the fuel and the core, continued ability to charge and discharge fuel. (author). 5 figs

AGR-1 Compact 5-3-1 Post-Irradiation Examination Results

Energy Technology Data Exchange (ETDEWEB)

Demkowicz, Paul [Idaho National Lab. (INL), Idaho Falls, ID (United States); Harp, Jason [Idaho National Lab. (INL), Idaho Falls, ID (United States); Winston, Phil [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ploger, Scott A. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-12-01

The Advanced Gas Reactor (AGR) Fuel Development and Qualification Program was established to perform the requisite research and development on tristructural isotropic (TRISO) coated particle fuel to support deployment of a high-temperature gas-cooled reactor (HTGR). The work continues as part of the Advanced Reactor Technologies (ART) TRISO Fuel program. The overarching program goal is to provide a baseline fuel qualification data set to support licensing and operation of an HTGR. To achieve these goals, the program includes the elements of fuel fabrication, irradiation, post-irradiation examination (PIE) and safety testing, fuel performance, and fission product transport (INL 2015). A series of fuel irradiation experiments is being planned and conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). These experiments will provide data on fuel performance under irradiation, support fuel process development, qualify the fuel for normal operating conditions, provide irradiated fuel for safety testing, and support the development of fuel performance and fission product transport models. The first of these irradiation tests, designated AGR-1, began in the ATR in December 2006 and ended in November 2009. This experiment was conducted primarily to act as a shakedown test of the multicapsule test train design and provide early data on fuel performance for use in fuel fabrication process development. It also provided samples for post-irradiation safety testing, where fission product retention of the fuel at high temperatures will be experimentally measured. The capsule design and details of the AGR-1 experiment have been presented previously.

AGR-1 Compact 1-3-1 Post-Irradiation Examination Results

Energy Technology Data Exchange (ETDEWEB)

Demkowicz, Paul Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-12-01

The Advanced Gas Reactor (AGR) Fuel Development and Qualification Program was established to perform the requisite research and development on tristructural isotropic (TRISO) coated particle fuel to support deployment of a high-temperature gas-cooled reactor (HTGR). The work continues as part of the Advanced Reactor Technologies (ART) TRISO Fuel program. The overarching program goal is to provide a baseline fuel qualification data set to support licensing and operation of an HTGR. To achieve these goals, the program includes the elements of fuel fabrication, irradiation, post-irradiation examination (PIE) and safety testing, fuel performance modeling, and fission product transport (INL 2015). A series of fuel irradiation experiments is being planned and conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). These experiments will provide data on fuel performance under irradiation, support fuel process development, qualify the fuel for normal operating conditions, provide irradiated fuel for safety testing, and support the development of fuel performance and fission product transport models. The first of these irradiation tests, designated AGR-1, began in the ATR in December 2006 and ended in November 2009. This experiment was conducted primarily to act as a shakedown test of the multicapsule test train design and provide early data on fuel performance for use in fuel fabrication process development. It also provided samples for post-irradiation safety testing, where fission product retention of the fuel at high temperatures will be experimentally measured. The capsule design and details of the AGR-1 experiment have been presented previously (Grover, Petti, and Maki 2010, Maki 2009).

AGR-1 Post Irradiation Examination Final Report

Energy Technology Data Exchange (ETDEWEB)

Demkowicz, Paul Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-08-01

The post-irradiation examination (PIE) of the Advanced Gas Reactor (AGR)-1 experiment was a multi-year, collaborative effort between Idaho National Laboratory (INL) and Oak Ridge National Laboratory (ORNL) to study the performance of UCO (uranium carbide, uranium oxide) tristructural isotropic (TRISO) coated particle fuel fabricated in the U.S. and irradiated at the Advanced Test Reactor at INL to a peak burnup of 19.6% fissions per initial metal atom. This work involved a broad array of experiments and analyses to evaluate the level of fission product retention by the fuel particles and compacts (both during irradiation and during post-irradiation heating tests to simulate reactor accident conditions), investigate the kernel and coating layer morphology evolution and the causes of coating failure, and explore the migration of fission products through the coating layers. The results have generally confirmed the excellent performance of the AGR-1 fuel, first indicated during the irradiation by the observation of zero TRISO coated particle failures out of 298,000 particles in the experiment. Overall release of fission products was determined by PIE to have been relatively low during the irradiation. A significant finding was the extremely low levels of cesium released through intact coatings. This was true both during the irradiation and during post-irradiation heating tests to temperatures as high as 1800°C. Post-irradiation safety test fuel performance was generally excellent. Silver release from the particles and compacts during irradiation was often very high. Extensive microanalysis of fuel particles was performed after irradiation and after high-temperature safety testing. The results of particle microanalysis indicate that the UCO fuel is effective at controlling the oxygen partial pressure within the particle and limiting kernel migration. Post-irradiation examination has provided the final body of data that speaks to the quality of the AGR-1 fuel, building

Advanced gas-cooled reactors (AGR)

Energy Technology Data Exchange (ETDEWEB)

Yeomans, R. M. [South of Scotland Electricity Board, Hunterston Power Station, West Kilbride, Ayshire, UK

1981-01-15

The paper describes the advanced gas-cooled reactor system, Hunterston ''B'' power station, which is a development of the earlier natural uranium Magnox type reactor. Data of construction, capital cost, operating performance, reactor safety and also the list of future developments are given.

Advanced Electron Microscopy and Micro analytical technique development and application for Irradiated TRISO Coated Particles from the AGR-1 Experiment

Energy Technology Data Exchange (ETDEWEB)

Van Rooyen, Isabella Johanna [Idaho National Lab. (INL), Idaho Falls, ID (United States); Lillo, Thomas Martin [Idaho National Lab. (INL), Idaho Falls, ID (United States); Wen, Haiming [Idaho National Lab. (INL), Idaho Falls, ID (United States); Wright, Karen Elizabeth [Idaho National Lab. (INL), Idaho Falls, ID (United States); Madden, James Wayne [Idaho National Lab. (INL), Idaho Falls, ID (United States); Aguiar, Jeffery Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2017-01-01

A series of up to seven irradiation experiments are planned for the Advanced Gas Reactor (AGR) Fuel Development and Quantification Program, with irradiation completed at the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for the first experiment (i.e., AGR-1) in November 2009 for an effective 620 full power days. The objective of the AGR-1 experiment was primarily to provide lessons learned on the multi-capsule test train design and to provide early data on fuel performance for use in fuel fabrication process development and post-irradiation safety testing data at high temperatures. This report describes the advanced microscopy and micro-analysis results on selected AGR-1 coated particles.

AGR-5/6/7 Irradiation Test Predictions using PARFUME

Energy Technology Data Exchange (ETDEWEB)

Skerjanc, William F. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2017-09-14

PARFUME, (PARticle FUel ModEl) a fuel performance modeling code used for high temperature gas-cooled reactors (HTGRs), was used to model the Advanced Gas Reactor (AGR)-5/6/7 irradiation test using predicted physics and thermal hydraulics data. The AGR-5/6/7 test consists of the combined fifth, sixth, and seventh planned irradiations of the AGR Fuel Development and Qualification Program. The AGR-5/6/7 test train is a multi-capsule, instrumented experiment that is designed for irradiation in the 133.4-mm diameter north east flux trap (NEFT) position of Advanced Test Reactor (ATR). Each capsule contains compacts filled with uranium oxycarbide (UCO) unaltered fuel particles. This report documents the calculations performed to predict the failure probability of tristructural isotropic (TRISO)-coated fuel particles during the AGR-5/6/7 experiment. In addition, this report documents the calculated source term from the driver fuel. The calculations include modeling of the AGR-5/6/7 irradiation that is scheduled to occur from October 2017 to April 2021 over a total of 13 ATR cycles, including nine normal cycles and four Power Axial Locator Mechanism (PALM) cycle for a total between 500 – 550 effective full power days (EFPD). The irradiation conditions and material properties of the AGR-5/6/7 test predicted zero fuel particle failures in Capsules 1, 2, and 4. Fuel particle failures were predicted in Capsule 3 due to internal particle pressure. These failures were predicted in the highest temperature compacts. Capsule 5 fuel particle failures were due to inner pyrolytic carbon (IPyC) cracking causing localized stresses concentrations in the SiC layer. This capsule predicted the highest particle failures due to the lower irradiation temperature. In addition, shrinkage of the buffer and IPyC layer during irradiation resulted in formation of a buffer-IPyC gap. The two capsules at the two ends of the test train, Capsules 1 and 5 experienced the smallest buffer-IPyC gap

Analysis of fission gas release-to-birth ratio data from the AGR irradiations

International Nuclear Information System (INIS)

Einerson, Jeffrey J.; Pham, Binh T.; Scates, Dawn M.; Maki, John T.; Petti, David A.

2016-01-01

A series of advanced gas reactor (AGR) irradiation tests is being conducted in the advanced test reactor (ATR) at Idaho National Laboratory (INL) in support of development and qualification of tristructural isotropic (TRISO) fuel used in the High temperature gas-cooled reactor (HTGR). Each AGR test consists of multiple independent capsules containing fuel compacts placed in a graphite cylinder shrouded by a steel shell. These capsules are instrumented with thermocouples (TC) embedded in the graphite enabling temperature control. For AGR-1, the first US irradiation of modern TRISO fuel completed in 2009, there were no particle failures detected. For AGR-2, a few exposed kernels existed in the fuel compacts based upon quality control data. For the AGR-3/4 experiment, particle failures in all capsules were expected because of the use of designed-to-fail (DTF) fuel particles whose kernels are identical to the driver fuel kernels and whose coatings are designed to fail under irradiation. The release-rate-to-birth-rate ratio (R/B) for each of krypton and xenon isotopes is calculated from release rates measured by the germanium detectors used in the AGR fission product monitoring (FPM) system installed downstream from each irradiated capsule. Birth rates are calculated based on the fission power in the experiment and fission product generation models. Thus, this R/B is a measure of the ability of fuel particle coating layers and compact matrix to retain fission gas atoms preventing their release into the sweep gas flow. The major factors that govern gaseous diffusion and release processes are found to be fuel material diffusion coefficient, temperature, and isotopic decay constant. To compare the release behavior among the AGR capsules and historic experiments, the R/B per failed particle is used. HTGR designers use this parameter in their fission product behavior models. For the U.S. TRISO fuel, a regression analysis is performed to establish functional relationships

Analysis of Fission Gas Release-to-Birth Ratio Data from the AGR Irradiations

International Nuclear Information System (INIS)

Einerson, Jeffrey J.; Pham, Binh T.; Scates, Dawn M.; Maki, John T.; Petti, David A.

2014-01-01

A series of Advanced Gas Reactor (AGR) irradiation tests is being conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) in support of development and qualification of tristructural isotropic (TRISO) fuel used in the High Temperature Gas-cooled Reactor (HTGR). Each AGR test consists of multiple independent capsules containing fuel compacts placed in a graphite cylinder shrouded by a steel shell. These capsules are instrumented with thermocouples (TC) embedded in the graphite enabling temperature control. For AGR-1, the first US irradiation of modern TRISO fuel completed in 2009, there were no particle failures detected. For AGR-2, a few exposed kernels existed in the fuel compacts based upon quality control data. For the AGR-3/4 experiment, particle failures in all capsules were expected because of the use of designed-to-fail (DTF) fuel particles whose kernels are identical to the driver fuel kernels and whose coatings are designed to fail under irradiation. The release-rate-to-birth-rate ratio (R/B) for each of krypton and xenon isotopes is calculated from release rates measured by the germanium detectors used in the AGR Fission Product Monitoring (FPM) System installed downstream from each irradiated capsule. Birth rates are calculated based on the fission power in the experiment and fission product generation models. Thus, this R/B is a measure of the ability of fuel particle coating layers and compact matrix to retain fission gas atoms preventing their release into the sweep gas flow. The major factors that govern gaseous diffusion and release processes are found to be fuel material diffusion coefficient, temperature, and isotopic decay constant. To compare the release behavior among the AGR capsules and historic experiments, the R/B per failed particle is used. HTGR designers use this parameter in their fission product behavior models. For the U.S. TRISO fuel, a regression analysis is performed to establish functional relationships

Analysis of fission gas release-to-birth ratio data from the AGR irradiations

Energy Technology Data Exchange (ETDEWEB)

Einerson, Jeffrey J., E-mail: jeffrey.einerson@inl.gov; Pham, Binh T.; Scates, Dawn M.; Maki, John T.; Petti, David A.

2016-09-15

A series of advanced gas reactor (AGR) irradiation tests is being conducted in the advanced test reactor (ATR) at Idaho National Laboratory (INL) in support of development and qualification of tristructural isotropic (TRISO) fuel used in the High temperature gas-cooled reactor (HTGR). Each AGR test consists of multiple independent capsules containing fuel compacts placed in a graphite cylinder shrouded by a steel shell. These capsules are instrumented with thermocouples (TC) embedded in the graphite enabling temperature control. For AGR-1, the first US irradiation of modern TRISO fuel completed in 2009, there were no particle failures detected. For AGR-2, a few exposed kernels existed in the fuel compacts based upon quality control data. For the AGR-3/4 experiment, particle failures in all capsules were expected because of the use of designed-to-fail (DTF) fuel particles whose kernels are identical to the driver fuel kernels and whose coatings are designed to fail under irradiation. The release-rate-to-birth-rate ratio (R/B) for each of krypton and xenon isotopes is calculated from release rates measured by the germanium detectors used in the AGR fission product monitoring (FPM) system installed downstream from each irradiated capsule. Birth rates are calculated based on the fission power in the experiment and fission product generation models. Thus, this R/B is a measure of the ability of fuel particle coating layers and compact matrix to retain fission gas atoms preventing their release into the sweep gas flow. The major factors that govern gaseous diffusion and release processes are found to be fuel material diffusion coefficient, temperature, and isotopic decay constant. To compare the release behavior among the AGR capsules and historic experiments, the R/B per failed particle is used. HTGR designers use this parameter in their fission product behavior models. For the U.S. TRISO fuel, a regression analysis is performed to establish functional relationships

A comparison of the observed and the expected cancers of the haematopoietic and lymphatic systems among workers at Windscale

International Nuclear Information System (INIS)

Dolphin, G.W.

1976-12-01

Data are given about the cases of cancers of the haematopoietic and lymphatic systems among workers at Windscale Works, BNFL during the period 1950 to 1974. The number of cancers of these types expected to occur in the working population at Windscale has been estimated for the same period. For none of these types is the observed number of cancers significantly different at the 95% confidence level from that expected. (author)

Precipitation in 20 Cr-25 Ni type stainless steel irradiated at low temperatures in a thermal reactor (AGR)

International Nuclear Information System (INIS)

Taylor, C.

1983-01-01

The effects of irradiation on the microstructure of AGR fuel rod cladding have been studied by analytical electron microscopy. Two alloys were investigated, the standard 20 Cr-25 Ni steel stabilised with Nb and a variant containing less Nb but strengthened with a dispersion of TiN precipitates. Irradiation at 360 deg C to 480 deg C produced (Ni, Si)-rich precipitates in both alloys; additionally the standard alloy contained (Ni, Nb, Si)-rich precipitates when irradiated at 440 deg C to 640 deg C. While similar features have been observed in other austenitic stainless steels irradiated in fast reactors, where the lattice-damage rate is greater than in a thermal reactor, their formation is not predicted by isothermal equilibrium diagrams. It is suggested here that the phases are irradiation-induced and that the total displacement damage is the controlling factor. Cladding solution-treated above 1050 deg C then irradiated at 2 -based reactor coolant occurred in cladding with low levels of cold-work at the outer surface, also resulting in Cr-rich carbide formation. (author)

Improvements in televisual and photographic inspections of AGRs

International Nuclear Information System (INIS)

Hayter, R.; Wadsworth, A.

1988-01-01

The visual inspection techniques and equipment used at AGR Power Stations have been improved and updated in the light of need and technological advance, new equipment being developed and introduced where necessary. Specifically this report covers the development and use of: a short TRIUMPH compatible photographic camera 600 mm long x 75 mm dia taking 50 shots on a 35 mm film; a 240 mm dia photographic pod taking high quality 70 mm format photographs of large in-reactor volumes; a photographic camera of cross section 37 x 17 mm for the inspection of helically wound AGR boilers and the subsequent development of this latter device into a state of the art TV inspection camera. (author)

Experience with a servo-hydraulic mechanical testing machine installed in a new shielded active facility at Windscale Nuclear Power Development Laboratories

International Nuclear Information System (INIS)

Garlick, A.; Hindmarch, P.; Gravenor, J.G.; Rhodes, D.

1982-03-01

An Instron model 1273 servo-hydraulic machine has been installed within a lead-shielded cell at Windscale in order to provide a facility capable of performing a wide range of mechanical tests on nuclear reactor structural materials and fuel assembly components. This particular type of machine was chosen because it has design features associated with the load frame, location of the actuator and adjustment and clamping of the cross-head that are especially well suited to remote operation within a shielded cell. The design of the testing facility is described and the programmes of work that have been completed over the past 11/2 years of operation are reviewed. (author)

Gas reactor and associated nuclear experience in the UK relevant to high temperature reactor engineering

International Nuclear Information System (INIS)

Beech, D.J.; May, R.

2000-01-01

In the UK, the NNC played a leading role in the design and build of all of the UK's commercial magnox reactors and advanced gas-cooled reactors (AGRs). It was also involved in the DRAGON project and was responsible for producing designs for large scale HTRs and other gas reactor designs employing helium and carbon dioxide coolants. This paper addresses the gas reactor experience and its relevance to the current HTR designs under development which use helium as the coolant, through the consideration of a representative sample of the issues addressed in the UK by the NNC in support of the AGR and other reactor programmes. Modern HTR designs provide unique engineering challenges. The success of the AGR design, reflected in the extended lifetimes agreed upon by the licensing authorities at many stations, indicates that these challenges can be successfully overcome. The UK experience is unique and provides substantial support to future gas reactor and high temperature engineering studies. (authors)

AGR 3/4 Irradiation Test Final As Run Report

Energy Technology Data Exchange (ETDEWEB)

Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-06-01

Several fuel and material irradiation experiments have been planned for the Idaho National Laboratory Advanced Reactor Technologies Technology Development Office Advanced Gas Reactor Fuel Development and Qualification Program (referred to as the INL ART TDO/AGR fuel program hereafter), which supports the development and qualification of tristructural-isotropic (TRISO) coated particle fuel for use in HTGRs. The goals of these experiments are to provide irradiation performance data to support fuel process development, qualify fuel for normal operating conditions, support development and validation of fuel performance and fission product transport models and codes, and provide irradiated fuel and materials for post irradiation examination and safety testing (INL 05/2015). AGR-3/4 combined the third and fourth in this series of planned experiments to test TRISO coated low enriched uranium (LEU) oxycarbide fuel. This combined experiment was intended to support the refinement of fission product transport models and to assess the effects of sweep gas impurities on fuel performance and fission product transport by irradiating designed-to-fail fuel particles and by measuring subsequent fission metal transport in fuel-compact matrix material and fuel-element graphite. The AGR 3/4 fuel test was successful in irradiating the fuel compacts to the burnup and fast fluence target ranges, considering the experiment was terminated short of its initial 400 EFPD target (Collin 2015). Out of the 48 AGR-3/4 compacts, 42 achieved the specified burnup of at least 6% fissions per initial heavy-metal atom (FIMA). Three capsules had a maximum fuel compact average burnup < 10% FIMA, one more than originally specified, and the maximum fuel compact average burnup was <19% FIMA for the remaining capsules, as specified. Fast neutron fluence fell in the expected range of 1.0 to 5.5×1025 n/m2 (E >0.18 MeV) for all compacts. In addition, the AGR-3/4 experiment was globally successful in keeping the

A computer model to predict temperatures and gas flows during AGR fuel handling

International Nuclear Information System (INIS)

Bishop, D.C.; Bowler, P.G.

1986-01-01

The paper describes the development of a comprehensive computer model (HOSTAGE) that has been developed for the Heysham II/Torness AGRs to predict temperature transients for all the important components during normal and fault conditions. It models not only the charge and discharge or fuel from an on-load reactor but also follows the fuel down the rest of the fuel route until it is dismantled. The main features of the physical model of gas and heat flow are described. Experimental results are used where appropriate and an indication will be given of how the predictions by HOSTAGE correlate with operating AGR reactors. The role of HOSTAGE in the Heysham II/Torness safety case is briefly discussed. (author)

An assessment of the radiological impact of the Windscale reactor fire, October 1957

International Nuclear Information System (INIS)

Crick, M.J.; Linsley, G.S.

1983-09-01

The assessment described has involved a review of previously unpublished data, in order to establish the quantities of nuclides released from materials undergoing irradiation in the pile at the time of the fire. Of these additional nuclides, only polonium-210 has been shown to make a significant contribution to the estimate of the collective effective dose equivalent to the population from the Windscale fire. The previous estimate of 1.2 x 10 3 man Sv for the collective effective dose equivalent commitment to the population of the UK and Northern Europe has been increased by 67% to 2.0 x 10 3 man Sv. This change is within the range of uncertainty of the original estimate. The influence of the addition on the theoretical estimate of the upper limit of possible health effects is discussed in this addendum and its foreword. With the inclusion of the additional nuclides, the inhalation pathway has become the overall largest contributor to this population dose, followed by the milk ingestion pathway; the largest nuclide contribution comes from iodine-131, followed by polonium-210. Some perspective may be provided on the contribution due to polonium-210 by noting that it is approximately one-tenth of that arising annually due to naturally occurring polonium-210, and less than one-hundredth of that due annually to the total natural background radiation. (author)

Building on the AGR experience

International Nuclear Information System (INIS)

Churchill, G.F.

1985-01-01

Experience with AGR reactors has indicated that quality assurance applied to procurement of plant and services throughout the hierarchy of purchasers and suppliers is a main area where there is scope for improvement. In view of this, improvements for procurement have been undertaken. These include a) the rationalisation of specified requirements for quality assurance systems, with the particular needs of each contract, and b) the rationalisation of purchasers' involvement in suppliers' quality assurance activities. Both aspects of procurement are described and discussed. (U.K.)

Nuclear power reactors

International Nuclear Information System (INIS)

1982-11-01

After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

AGR-3/4 Final Data Qualification Report for ATR Cycles 151A through 155B-1

Energy Technology Data Exchange (ETDEWEB)

Pham, Binh T. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-03-01

This report provides the qualification status of experimental data for the entire Advanced Gas Reactor 3/4 (AGR 3/4) fuel irradiation. AGR-3/4 is the third in a series of planned irradiation experiments conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) for the AGR Fuel Development and Qualification Program, which supports development of the advanced reactor technology under the INL ART Technology Development Office (TDO). The main objective of AGR-3/4 irradiation is to provide a known source of fission products for subsequent transport through compact matrix and structural graphite materials due to the presence of designed-to-fail fuel particles. Full power irradiation of the AGR 3/4 test began on December 14, 2011 (ATR Cycle 151A), and was completed on April 12, 2014 (end of ATR Cycle 155B) after 369.1 effective full power days of irradiation. The AGR-3/4 test was in the reactor core for eight of the ten ATR cycles between 151A and 155B. During the unplanned outage cycle, 153A, the experiment was removed from the ATR northeast flux trap (NEFT) location and stored in the ATR canal. This was to prevent overheating of fuel compacts due to higher than normal ATR power during the subsequent Powered Axial Locator Mechanism cycle, 153B. The AGR 3/4 test was inserted back into the ATR NEFT location during the outage of ATR Cycle 154A on April 26, 2013. Therefore, the AGR-3/4 irradiation data received during these 2 cycles (153A and 153B) are irrelevant and their qualification status isnot included in this report. Additionally, during ATR Cycle 152A the ATR core ran at low power for a short enough duration that the irradiation data are not used for physics and thermal calculations. However, the qualification status of irradiation data for this cycle is still covered in this report. As a result, this report includes data from 8 ATR Cycles: 151A, 151B, 152A, 152B, 154A, 154B, 155A, and 155B, as recorded in the Nuclear Data Management and

The calculation of methane profiles in AGR graphite structures

International Nuclear Information System (INIS)

Faircloth, R.L.; Harper, A.

1981-07-01

The MEDIC model has been extended in order that it may be applied to experiments carried out in the Windscale Advanced Gas Cooled Reactor (WAGR) to measure graphite radiolytic oxidation rates in thick specimens. Three aspects are covered: (a) the extension of the analysis of conventional WAGR nest assemblies to two dimensions rather than the infinite cylinder situation used in current assessments; (b) the examination of the effect of possible paths in WAGR nests; and (c) application of the model to the more complex geometry associated with WAGR inverted nest and rod type assemblies. It is demonstrated that only small errors are introduced into the analysis of WAGR nest data by making the assumption of infinite cylinder geometry. The effect of leakage paths within the nest assembly is also shown to be probably unimportant. (author)

CO{sub 2} direct cycles suitable for AGR type reactors; Cycles directs de gaz carbonique applicables aux reacteurs du genre AGR

Energy Technology Data Exchange (ETDEWEB)

Maillet, E [Commissariat a l' Energie Atomique. Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

1967-10-01

The perspectives given by the gas turbines under pressure, to build simple nuclear power plants and acieving significantly high yield, are specified. The CO{sub 2} is characterised by by good efficiency under moderate temperature (500 to 750 Celsius degrees), compactness and the simpleness of machines and the safe exploitation (supply, storage, relief cooling, thermosyphon). The revision of thermal properties of the CO{sub 2} and loss elements show that several direct cycles would fit in particular to the AGR type reactors. Cycles that would diverge a little from classical models and able to lead to power and heat generation can lead by simple means to the best results. Several satisfying solutions present for the starting up, the power regulation and the stopping. The nuclear power plant components and the functioning safety are equally considered in the present report. The conclusions stimulate the studies and realizations of carbon dioxide gas turbines in when approprite. [French] Les perspectives offertes par la turbine a gaz sous pression, pour construire des centrales nucleaires simples et de rendement progressivement eleve, se precisent actuellement. le CO{sub 2} se distingue par sa bonne efficacite a temperature moderee (500 a 750 degres celsius), la compacite et la simplicite des machines, et la surete qu'il apporte a l'exploitation ( approvisionnement, stockage, refroidissement de secours, thermosiphon). La revision des proprietes thermophysiques du CO{sub 2} et des elements de pertes montre que divers cycles directs conviendraient en particulier aux reacteurs agr ou derives. Des cycles s'ecartant peu des modeles classiques, et se pretant ulterieurement a la production simultanee d'electricite et de chaleur, peuvent conduire par des moyens simples aux meilleurs resultats d'ensemble. Plusieurs solutions satisfaisantes se presentent pour le demarrage, le reglage de la puissance et l'arret. Les composants de la centrale et la surete de fonctionnement sont

Chapter 10: Calculation of the temperature coefficient of reactivity of a graphite-moderated reactor

International Nuclear Information System (INIS)

Brown, G.; Richmond, R.; Stace, R.H.W.

1963-01-01

The temperature coefficients of reactivity of the BEPO, Windscale and Calder reactors are calculated, using the revised methods given by Lockey et al. (1956) and by Campbell and Symonds (1962). The results are compared with experimental values. (author)

Advances in AGR fuel fabrication - now and the future

International Nuclear Information System (INIS)

Bleasdale, P.A.

1995-01-01

To date, over 3 million AGR fuel pins have been manufactured at Springfields for the UK AGR programme. During this time, AGR fuel design and manufacture has developed and evolved in response to the needs of the reactor operators to enhance fuel reliability and performance. More recently, major advances have been made in the systems and organisational culture which support fuel manufacture at Fuel Division. The introduction of MRP II in 1989 into Fuel Division enabled significant reductions in stock and work-in-progress, together with reductions in manufacturing lead times. Other successful initiatives introduced into Fuel Division have been Just-in-Time (JIT) and AST (Additional Skills Training) which have built on the success of MRP II. All of these initiatives are evidence of Fuel Division's ''Total Quality'' approach to fabricating fuel. Fuel Division is currently in the final stages of commissioning the New Oxide Fuels Complex (NOFC) where both AGR and PWR fuel will be manufactured to the highest standards of quality, safety and environmental protection. NOFC is a totally integrated plant which represents a Pound 200M investment, demonstrating Fuel Division's commitment to building on its 40+ years of fuel fabrication experience and ensuring secure supply of fuel to its customers for years to come. (author)

Ceramography of Irradiated tristructural isotropic (TRISO) Fuel from the AGR-2 Experiment

Energy Technology Data Exchange (ETDEWEB)

Rice, Francine Joyce [Idaho National Lab. (INL), Idaho Falls, ID (United States); Stempien, John Dennis [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-09-01

Ceramography was performed on cross sections from four tristructural isotropic (TRISO) coated particle fuel compacts taken from the AGR-2 experiment, which was irradiated between June 2010 and October 2013 in the Advanced Test Reactor (ATR). The fuel compacts examined in this study contained TRISO-coated particles with either uranium oxide (UO2) kernels or uranium oxide/uranium carbide (UCO) kernels that were irradiated to final burnup values between 9.0 and 11.1% FIMA. These examinations are intended to explore kernel and coating morphology evolution during irradiation. This includes kernel porosity, swelling, and migration, and irradiation-induced coating fracture and separation. Variations in behavior within a specific cross section, which could be related to temperature or burnup gradients within the fuel compact, are also explored. The criteria for categorizing post-irradiation particle morphologies developed for AGR-1 ceramographic exams, was applied to the particles in the AGR-2 compacts particles examined. Results are compared with similar investigations performed as part of the earlier AGR-1 irradiation experiment. This paper presents the results of the AGR-2 examinations and discusses the key implications for fuel irradiation performance.

Readiness Review of BWXT for Fabrication of AGR 5/6/7 Compacts

Energy Technology Data Exchange (ETDEWEB)

Marshall, Douglas William [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sharp, Michelle Tracy [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2017-02-01

In support of preparations for fabricating compacts for the Advanced Gas Reactor (AGR) fuel qualification irradiation experiments (AGR-5/6/7), Idaho National Laboratory (INL) conducted a readiness review of the BWX Technology (BWXT) procedures, processes, and equipment associated with compact fabrication activities at the BWXT Nuclear Operations Group (BWXT-NOG) facility outside Lynchburg, VirginiaVA. The readiness review used quality assurance requirements taken from the American Society of Mechanical Engineers (ASME) Nuclear Quality Assurance Standard (NQA-1-2008/1a-2009) as a basis to assess readiness to start compact fabrication.

Nuclear power. The Windscale controversy

International Nuclear Information System (INIS)

Boyle, G.

1978-01-01

The aims of this unit are: (1) to provide a basic understanding of nuclear technology and of the associated technical and environmental problems; (2) to provide an understanding of: (a) the historical growth of the nuclear industry; (b) the arguments for the continued development of nuclear power, and the institutions promoting that development; (3) to provide a basic understanding of the mechanisms and institutions which officially regulate the nuclear power programme in the UK; (4) to provide an understanding of the main issues - technical, economic, social and political - involved in the controversy over the proposed expansion of British Nuclear Fuels Ltd's reprocessing facilities at Windscale, and the events leading up to the Public Inquiry on the proposal which began in June 1977; and (5) to examine (a) the reason for the growth in opposition to nuclear power in various countries and the different approaches taken by the opposition groups; (b) the political impact and effectiveness of that opposition. (author)

Design and development of steam generators for the AGR power stations at Heysham II/Torness

Energy Technology Data Exchange (ETDEWEB)

Charcharos, A N; Jones, A G [National Nuclear Corp. Ltd., Cheshire (United Kingdom)

1984-07-01

The current AGR steam generator design is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley/Hunterston AGR power stations. These units have demonstrated proven control and reliability in service. In this paper the factors which have dictated the design and layout of the latest AGR steam generators are described and reference made to the latest high temperature design techniques that have been employed. Details of development work to support the design and establish the performance characteristics over the range of plant operating conditions are also given. To comply with current UK safety standards, the AGR steam generators and associated plant are designed to accommodate seismic loadings. In addition, provision is made for an independent heat removal system for post reactor trip operations. (author)

Design and development of steam generators for the AGR power stations at Heysham II/Torness

International Nuclear Information System (INIS)

Charcharos, A.N.; Jones, A.G.

1984-01-01

The current AGR steam generator design is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley/Hunterston AGR power stations. These units have demonstrated proven control and reliability in service. In this paper the factors which have dictated the design and layout of the latest AGR steam generators are described and reference made to the latest high temperature design techniques that have been employed. Details of development work to support the design and establish the performance characteristics over the range of plant operating conditions are also given. To comply with current UK safety standards, the AGR steam generators and associated plant are designed to accommodate seismic loadings. In addition, provision is made for an independent heat removal system for post reactor trip operations. (author)

AGR-1 Irradiation Test Final As-Run Report, Rev. 3

Energy Technology Data Exchange (ETDEWEB)

Collin, Blaise P. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-01-01

This document presents the as-run analysis of the AGR-1 irradiation experiment. AGR-1 is the first of eight planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the US Department of Energy (DOE) as part of the Next-Generation Nuclear Plant (NGNP) project. The objectives of the AGR-1 experiment are: 1. To gain experience with multi-capsule test train design, fabrication, and operation with the intent to reduce the probability of capsule or test train failure in subsequent irradiation tests. 2. To irradiate fuel produced in conjunction with the AGR fuel process development effort. 3. To provide data that will support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. In order to achieve the test objectives, the AGR-1 experiment was irradiated in the B-10 position of the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL) for a total duration of 620 effective full power days of irradiation. Irradiation began on December 24, 2006 and ended on November 6, 2009 spanning 13 ATR cycles and approximately three calendar years. The test contained six independently controlled and monitored capsules. Each capsule contained 12 compacts of a single type, or variant, of the AGR coated fuel. No fuel particles failed during the AGR-1 irradiation. Final burnup values on a per compact basis ranged from 11.5 to 19.6 %FIMA, while fast fluence values ranged from 2.21 to 4.39 x 10²⁵ n/m² (E >0.18 MeV). We’ll say something here about temperatures once thermal recalc is done. Thermocouples performed well, failing at a lower rate than expected. At the end of the irradiation, nine of the originally-planned 19 TCs were considered functional. Fission product release-to-birth (R/B) ratios were quite low. In most capsules, R/B values at the end of the irradiation were at or below

Windscale inquiry and policy-making procedures

Energy Technology Data Exchange (ETDEWEB)

Von Moltke, K

1978-07-01

Policy decisions on the development and installation of nuclear facilities often strain both the time and human resources of a country, some countries having taken steps to involve the national government in specific siting decisions and shifting the constitutional balance in response to popular dissent. Challenges to nuclear facilities could be met by limiting the scope of intervenors and the use of judicial review. The 100-day Windscale Inquiry in the United Kingdom represents the most costly review any country has had of a specific nuclear policy and has international implications. A chronology of the inquiry illustrates how the debate evolved into a vote on whether nuclear energy should be developed at all and effectively cut off other avenues of recourse. The traditional procedures for planning are shown to be inadequate for setting nuclear energy policy without the intervention of Parliament. 18 references.

A description of nuclear reactor accidents and their consequences

International Nuclear Information System (INIS)

Murray, A.

1989-01-01

Nuclear reactor accidents which have caused core damage, released a significant amount of radioactivity, or caused death or serious injury are described. The reactor accidents discussed in detail include Chernobyl, Three Mile Island, SL-1 and Windscale, although information on other less consequential accidents is also provided. The consequences of these accidents are examined in terms of the amounts of radioactivity released, the radiation doses received, and remedial actions and interventions taken following the accident. 10 refs., 1 fig., 2 tabs

Uncertainty Quantification of Calculated Temperatures for the U.S. Capsules in the AGR-2 Experiment

Energy Technology Data Exchange (ETDEWEB)

Lybeck, Nancy [Idaho National Lab. (INL), Idaho Falls, ID (United States); Einerson, Jeffrey J. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Pham, Binh T. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hawkes, Grant L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-03-01

A series of Advanced Gas Reactor (AGR) irradiation experiments are being conducted within the Advanced Reactor Technology (ART) Fuel Development and Qualification Program. The main objectives of the fuel experimental campaign are to provide the necessary data on fuel performance to support fuel process development, qualify a fuel design and fabrication process for normal operation and accident conditions, and support development and validation of fuel performance and fission product transport models and codes (PLN-3636). The AGR-2 test was inserted in the B-12 position in the Advanced Test Reactor (ATR) core at Idaho National Laboratory (INL) in June 2010 and successfully completed irradiation in October 2013, resulting in irradiation of the TRISO fuel for 559.2 effective full power days (EFPDs) during approximately 3.3 calendar years. The AGR-2 data, including the irradiation data and calculated results, were qualified and stored in the Nuclear Data Management and Analysis System (NDMAS) (Pham and Einerson 2014). To support the U.S. TRISO fuel performance assessment and to provide data for validation of fuel performance and fission product transport models and codes, the daily as-run thermal analysis has been performed separately on each of four AGR-2 U.S. capsules for the entire irradiation as discussed in (Hawkes 2014). The ABAQUS code’s finite element-based thermal model predicts the daily average volume-average fuel temperature and peak fuel temperature in each capsule. This thermal model involves complex physical mechanisms (e.g., graphite holder and fuel compact shrinkage) and properties (e.g., conductivity and density). Therefore, the thermal model predictions are affected by uncertainty in input parameters and by incomplete knowledge of the underlying physics leading to modeling assumptions. Therefore, alongside with the deterministic predictions from a set of input thermal conditions, information about prediction uncertainty is instrumental for the ART

Measurements of fuel temperature coefficient of reactivity on a commercial AGR

International Nuclear Information System (INIS)

Telford, A.; Bridge, M.J.

1978-01-01

Tests have been carried out on the commercial AGR at Hikley Point to determine the fuel temperature coefficient of reactivity, an important safety related parameter. Reactor neutron flux was measured during transients induced by movement of a bank of control rods from one steady position to another. An inverse kinetics analysis was applied to the measured flux to determine the change which occured in core reactivity as the fuel temperature changed. The variation of mean fuel temperature was deduced from the flux transient by means of a nine-plane thermal hydraulics representation of the AGR fuel channel. Results so far obtained confirm the predicted variation of fuel temperature coefficient with butn-up. (author)

Consequences of Windscale accident (October 1957) and study of the validity of the Sutton's mathematical model of atmospheric diffusion (1960)

International Nuclear Information System (INIS)

Doury, A.

1960-01-01

The reactor accident that happens at the number 1 pile of Windscale in 1957 was followed by a discharge of radioactive products into the atmosphere from the 1.X.1957 at 4.30 PM to the 12.X.1957 at 3.10 PM. On october the 11 th it was possible to say that there was no more risk either of external irradiation or inhalation. But in adopting a M.A.C. of 0,1 μcurie of iodine 131 per litre of milk, the Authority had to control the milk delivery till november 23 rd on a 500 km 2 area. On the other hand, this exceptional accident permit to verify that Sutton's atmospheric diffusion model could give an easy means to foresee, with a sufficient approximation, the consequences of a dispersion of radioactive products into the atmosphere. (author) [fr

Consequences of Windscale accident (October 1957) and study of the validity of the Sutton's mathematical model of atmospheric diffusion (1960); Etude des consequences de l'accident de Windscale (Octobre 1957) et de la validite du modele mathematique de diffusion atmospherique de Sutton (1960)

Energy Technology Data Exchange (ETDEWEB)

Doury, A [Commissariat a l' Energie Atomique (S.C.R.G.R.) Saclay (France).Centre d' Etudes Nucleaires; Martin, J J [Electricite de France (EDF)(S.L.P.R.), 37 - Chinon (France)

1960-07-01

The reactor accident that happens at the number 1 pile of Windscale in 1957 was followed by a discharge of radioactive products into the atmosphere from the 1.X.1957 at 4.30 PM to the 12.X.1957 at 3.10 PM. On october the 11{sup th} it was possible to say that there was no more risk either of external irradiation or inhalation. But in adopting a M.A.C. of 0,1 {mu}curie of iodine 131 per litre of milk, the Authority had to control the milk delivery till november 23{sup rd} on a 500 km{sup 2} area. On the other hand, this exceptional accident permit to verify that Sutton's atmospheric diffusion model could give an easy means to foresee, with a sufficient approximation, the consequences of a dispersion of radioactive products into the atmosphere. (author) [French] L'accident survenu a la pile numero 1 de Windscale en 1957 a entraine l'emission de matieres radioactives dans l'atmosphere du 10 octobre a 16h30 au 12 octobre a 15h10. Le 11 octobre, on pouvait dire qu'il n'y avait plus de risque d'irradiation externe ni de danger par inhalation. Mais en adoptant une C.M.A. de 0,1 {mu}curie d'iode 131 par litre de lait, les autorites ont du reglementer la consommation du lait jusqu'au 23 novembre sur une etendue d'environ 500 km{sup 2}. D'autre part, cet accident exceptionnel a permis de verifier que le modele de diffusion atmospherique de Sutton pouvait fournir un moyen commode de prevoir avec une approximation suffisante les consequences d'une dispersion de produits radioactifs dans l'atmosphere. (auteur)

STATUS OF TRISO FUEL IRRADIATIONS IN THE ADVANCED TEST REACTOR SUPPORTING HIGH-TEMPERATURE GAS-COOLED REACTOR DESIGNS

Energy Technology Data Exchange (ETDEWEB)

Davenport, Michael; Petti, D. A.; Palmer, Joe

2016-11-01

The United States Department of Energy’s Advanced Reactor Technologies (ART) Advanced Gas Reactor (AGR) Fuel Development and Qualification Program is irradiating up to seven low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States. The experiments will be irradiated over the next several years to demonstrate and qualify new TRISO coated particle fuel for use in high temperature gas reactors. The goals of the experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of several independent capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006 and was completed in November 2009. The second experiment (AGR-2) started irradiation in June 2010 and completed in October 2013. The third and fourth experiments have been combined into a single experiment designated (AGR-3/4), which started its irradiation in December 2011 and completed in April 2014. Since the purpose of this experiment was to provide data on fission product migration and retention in the NGNP reactor, the design of this experiment was significantly different from the first two experiments, though the control

The Windscale Inquiry - A U.K. Exercise in Nuclear Regulation

International Nuclear Information System (INIS)

Bolter, Harold.

1978-01-01

This paper describes the Public Inquiry opened on 14 June 1977 concerning extenssion of the Windscale plant and the events preceding it. Four issues were considered: the implications of the proposed development for public safety; those for other aspects of the national interest; those of plant construction and operation for the environment: the measures that could be adopted under existing U.K. legislation, particularly under the Radioactive Substances Act 1960 to control waste disposal, and under the Nuclear Installations Act 1965 to provide for the safety of operations, and finally, other implications for the locality. (NEA) [fr

The Windscale inquiry and its impact on the national nuclear programme

International Nuclear Information System (INIS)

Bolter, H.E.

1978-01-01

This lecture by the Director of Information Services, British Nuclear Fuels Ltd., endeavours to convey something of the flavour of the recent Windscale Inquiry that lasted for 100 days and the results of which encompassed about four million words. It is stated that in at least the short term nuclear power in this country will only expand at a rate that is acceptable to the general public, largely as influenced by members of parliament and the media, including the press. It probably will not expand at a rate acceptable to scientists or deemed necessary by them. The pressure that led to the inquiry will not lessen because the inquiry is over; if anything it will increase. Nevertheless, eventually the nuclear power industry must win and the public will be forced to learn to live with it since the alternative, a society short of energy, is intolerable. Unless the industry has a reasonably consistent work load and a reasonably consistent demand for its products it will become moribund. Comparisons are made with the history of the coal industry. It is believed that one of the main lessons to be learnt form the Windscale Inquiry is that the Nuclear Power Industry's immediate future lies largely in its own hands. An outline is included of the past and probable future work of British Nuclear Fuels Ltd. with emphasis on the reprocessing of irradiated oxide fuel. (author)

The Windscale file. A lay-guide to living (and dying) with a nuclear neighbour

International Nuclear Information System (INIS)

1983-01-01

Greenpeace have commissioned four reports from 'The Political Ecology Research Group' associated with the import of spent nuclear fuel to the UK and the reprocessing of spent nuclear fuel rods at Windscale. Since 1980 Greenpeace has campaigned against these activities. This booklet based on these four reports has been produced to translate their findings into a more popular and readable form. (U.K.)

Steam up over reactor policy

International Nuclear Information System (INIS)

Kovan, D.

1976-01-01

Britain is once more assessing its nuclear power programme in the light of recent forecasts that there is unlikely to be any growth in the demand for electricity for many years to come. This means that the extra costs of launching a commercially unproven reactor, the Steam Generating Heavy Water Reactor (SGHWR), will be an even greater burden than previously expected, because they would be spread over fewer reactors. Sir John Hill's reported assessment concludes that the present strategy would be the most expensive way of developing Britain's nuclear power programme; and under the circumstances, may not be the best option. The SGHWR programme will certainly be more expensive than either relaunching a programme of advanced gas-cooled reactors (AGRs), or building American designed pressurised water reactors (PWRs). Recent developments of the AGR and PWR's and their advantages in the present position are outlined. (U.K.)

After the fire: preparing the Windscale Piles for decommissioning

International Nuclear Information System (INIS)

Anon.

1990-01-01

The Windscale Piles in the UK were taken out of service in 1957 after a fire in Pile 1. They have remained essentially in the same state since that time and during this period there have been periodic inspections of the complete structures to ensure that there is no degradation taking place. The Piles are in a safe condition and would remain so for a considerable period (50 years or more) provided they were undisturbed. However, the Piles must be decommissioned at some time and clearly this will require preparatory work which is now being carried out. The work is scheduled for completion in 1994, at a cost of Pound 8 million at present day prices. (author)

Chemical cleaning of UK AGR boilers

International Nuclear Information System (INIS)

Rudge, A.; Turner, P.; Ghosh, S.; Clary, W.; Tice, D.R.

2002-01-01

For a number of years, the waterside pressure drops across the advanced gas-cooled reactor (AGR) pod boilers have been increasing. The pressure drop increases have accelerated with time, which is the converse behaviour to that expected for rippled magnetite formation (rapid initial increase slowing down with time). Nonetheless, magnetite deposition remains the most likely cause for the increasing boiler resistances. A number of potential countermeasures have been considered in response to the boiler pressure drop increases. However, there was no detectable reduction in the rate of pressure drop increase. Chemical cleaning was therefore considered and a project to substantiate and then implement chemical cleaning was initiated. (authors)

Thinking about Windscale

Energy Technology Data Exchange (ETDEWEB)

Longhurst, A.R.

1977-10-01

In his editorial the author states that the public enquiry into the future of nuclear fuel reprocessing at Windscale raised the question of how the public is best served in such matters; in both Britain and the US, the format in which public interest is determined is usually fallacious. There is seldom sufficient distinction between questions of public interest and those of scientific fact. The complexity of ecology and how limited our understanding of it is are often obscured during public examination of environmental questions. If scientists fail to agree, why should agreement, or resolution of disagreement be expected within public enquiries which allow little chance for challenging expert statements or re-examining data. To help this situation, the US requires Environmental Impact Statements which permit rational challenging. In addition in the US, there is an attempt to formalize the challenge between scientific witnesses at hearings so that the adversary can be deemed to have proved a case. The proposal is, that for major issues, a Science Court should judge the merits of opposing arguments. Under discussion is a test of the concept to clarify and codify procedural rules. The importance of the principle inherent in the impact statement and Science Court must be recognized. Only by such radical departures from traditional ways of determining public interest can we come to grips with the gap between the ability of environmental science to give clear decisions and the ability assumed (by public and administrators) to exist within environmental science. Those in Europe, because of the rapidity with which the world is changing, should be receptive to new and perhaps difficult ways of meeting the challenges of the environmental crisis.

Design aspects of water usage in the Windscale nuclear fuel reprocessing plants

International Nuclear Information System (INIS)

Wharton, J.; Bullock, M.J.

1982-01-01

The safeguard requirements of a nuclear fuel reprocessing plant place unique constraints on a designer which, in turn, affect the scope for the exercise of water economy. These constraints are examined within the context of the British Nuclear Fuels Limited reprocessing plants at Windscale and indicate the scope for water conservation. The plants and their design principles are described with particular reference to water services and usage. Progressive design development is discussed to illustrate the increasing importance of water economy. (author)

The UK gas-cooled reactor programme - Progress report 1988

International Nuclear Information System (INIS)

Askew, J.R.

1989-01-01

This paper summarises key developments during 1988 on the 26 Magnox reactors and 14 AGRs now operating in the UK. Details are given of long-term safety reviews of the Berkeley and Bradwell Magnox stations which resulted in a decision by CEGB to cease generation at Berkeley but to continue operation at Bradwell. The summary of operating experience with the AGRs concentrates on the completion of construction and successful commissioning of the second generation AGRs at Heysham 2 and Torness. An appended article by John Wilson, Deputy Director of the UKAEA's gas-cooled reactor R and D programme, gives details of the aims and achievements of the programme during 1988. (author)

Improving thermal model prediction through statistical analysis of irradiation and post-irradiation data from AGR experiments

International Nuclear Information System (INIS)

Pham, Binh T.; Hawkes, Grant L.; Einerson, Jeffrey J.

2014-01-01

As part of the High Temperature Reactors (HTR) R and D program, a series of irradiation tests, designated as Advanced Gas-cooled Reactor (AGR), have been defined to support development and qualification of fuel design, fabrication process, and fuel performance under normal operation and accident conditions. The AGR tests employ fuel compacts placed in a graphite cylinder shrouded by a steel capsule and instrumented with thermocouples (TC) embedded in graphite blocks enabling temperature control. While not possible to obtain by direct measurements in the tests, crucial fuel conditions (e.g., temperature, neutron fast fluence, and burnup) are calculated using core physics and thermal modeling codes. This paper is focused on AGR test fuel temperature predicted by the ABAQUS code's finite element-based thermal models. The work follows up on a previous study, in which several statistical analysis methods were adapted, implemented in the NGNP Data Management and Analysis System (NDMAS), and applied for qualification of AGR-1 thermocouple data. Abnormal trends in measured data revealed by the statistical analysis are traced to either measuring instrument deterioration or physical mechanisms in capsules that may have shifted the system thermal response. The main thrust of this work is to exploit the variety of data obtained in irradiation and post-irradiation examination (PIE) for assessment of modeling assumptions. As an example, the uneven reduction of the control gas gap in Capsule 5 found in the capsule metrology measurements in PIE helps identify mechanisms other than TC drift causing the decrease in TC readings. This suggests a more physics-based modification of the thermal model that leads to a better fit with experimental data, thus reducing model uncertainty and increasing confidence in the calculated fuel temperatures of the AGR-1 test

Improving thermal model prediction through statistical analysis of irradiation and post-irradiation data from AGR experiments

Energy Technology Data Exchange (ETDEWEB)

Pham, Binh T., E-mail: Binh.Pham@inl.gov [Human Factor, Controls and Statistics Department, Nuclear Science and Technology, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Hawkes, Grant L. [Thermal Science and Safety Analysis Department, Nuclear Science and Technology, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Einerson, Jeffrey J. [Human Factor, Controls and Statistics Department, Nuclear Science and Technology, Idaho National Laboratory, Idaho Falls, ID 83415 (United States)

2014-05-01

As part of the High Temperature Reactors (HTR) R and D program, a series of irradiation tests, designated as Advanced Gas-cooled Reactor (AGR), have been defined to support development and qualification of fuel design, fabrication process, and fuel performance under normal operation and accident conditions. The AGR tests employ fuel compacts placed in a graphite cylinder shrouded by a steel capsule and instrumented with thermocouples (TC) embedded in graphite blocks enabling temperature control. While not possible to obtain by direct measurements in the tests, crucial fuel conditions (e.g., temperature, neutron fast fluence, and burnup) are calculated using core physics and thermal modeling codes. This paper is focused on AGR test fuel temperature predicted by the ABAQUS code's finite element-based thermal models. The work follows up on a previous study, in which several statistical analysis methods were adapted, implemented in the NGNP Data Management and Analysis System (NDMAS), and applied for qualification of AGR-1 thermocouple data. Abnormal trends in measured data revealed by the statistical analysis are traced to either measuring instrument deterioration or physical mechanisms in capsules that may have shifted the system thermal response. The main thrust of this work is to exploit the variety of data obtained in irradiation and post-irradiation examination (PIE) for assessment of modeling assumptions. As an example, the uneven reduction of the control gas gap in Capsule 5 found in the capsule metrology measurements in PIE helps identify mechanisms other than TC drift causing the decrease in TC readings. This suggests a more physics-based modification of the thermal model that leads to a better fit with experimental data, thus reducing model uncertainty and increasing confidence in the calculated fuel temperatures of the AGR-1 test.

Graphite core design in UK reactors

International Nuclear Information System (INIS)

Davies, M.W.

1996-01-01

The cores in the first power producing Magnox reactors in the UK were designed with only a limited amount of information available regarding the anisotropic dimensional change behaviour of Pile Grade graphite. As more information was gained it was necessary to make modifications to the design, some minor, some major. As the cores being built became larger, and with the switch to the Advanced Gas-cooled Reactor (AGR) with its much higher power density, additional problems had to be overcome such as increased dimensional change and radiolytic oxidation by the carbon dioxide coolant. For the AGRs a more isotropic graphite was required, with a lower initial open pore volume and higher strength. Gilsocarbon graphite was developed and was selected for all the AGRs built in the UK. Methane bearing coolants are used to limit radiolytic oxidation. (author). 5 figs

Advanced gas cooled reactors - Designing for safety

International Nuclear Information System (INIS)

Keen, Barry A.

1990-01-01

The Advanced Gas-Cooled Reactor Power Stations recently completed at Heysham in Lancashire, England, and Torness in East Lothian, Scotland represent the current stage of development of the commercial AGR. Each power station has two reactor turbo-generator units designed for a total station output of 2x660 MW(e) gross although powers in excess of this have been achieved and it is currently intended to uprate this as far as possible. The design of both stations has been based on the successful operating AGRs at Hinkley Point and Hunterston which have now been in-service for almost 15 years, although minor changes were made to meet new safety requirements and to make improvements suggested by operating experience. The construction of these new AGRs has been to programme and within budget. Full commercial load for the first reactor at Torness was achieved in August 1988 with the other three reactors following over the subsequent 15 months. This paper summarises the safety principles and guidelines for the design of the reactors and discusses how some of the main features of the safety case meet these safety requirements. The paper also summarises the design problems which arose during the construction period and explains how these problems were solved with the minimum delay to programme

Advanced gas cooled reactors - Designing for safety

Energy Technology Data Exchange (ETDEWEB)

Keen, Barry A [Engineering Development Unit, NNC Limited, Booths Hall, Knutsford, Cheshire (United Kingdom)

1990-07-01

The Advanced Gas-Cooled Reactor Power Stations recently completed at Heysham in Lancashire, England, and Torness in East Lothian, Scotland represent the current stage of development of the commercial AGR. Each power station has two reactor turbo-generator units designed for a total station output of 2x660 MW(e) gross although powers in excess of this have been achieved and it is currently intended to uprate this as far as possible. The design of both stations has been based on the successful operating AGRs at Hinkley Point and Hunterston which have now been in-service for almost 15 years, although minor changes were made to meet new safety requirements and to make improvements suggested by operating experience. The construction of these new AGRs has been to programme and within budget. Full commercial load for the first reactor at Torness was achieved in August 1988 with the other three reactors following over the subsequent 15 months. This paper summarises the safety principles and guidelines for the design of the reactors and discusses how some of the main features of the safety case meet these safety requirements. The paper also summarises the design problems which arose during the construction period and explains how these problems were solved with the minimum delay to programme.

Gas Reactor International Cooperative Program. Interim report. Construction and operating experience of selected European Gas-Cooled Reactors

International Nuclear Information System (INIS)

1978-09-01

The construction and operating experience of selected European Gas-Cooled Reactors is summarized along with technical descriptions of the plants. Included in the report are the AVR Experimental Pebble Bed Reactor, the Dragon Reactor, AGR Reactors, and the Thorium High Temperature Reactor (THTR). The study demonstrates that the European experience has been favorable and forms a good foundation for the development of Advanced High Temperature Reactors

Large packages for reactor decommissioning waste

International Nuclear Information System (INIS)

Price, M.S.T.

1991-01-01

This study was carried out jointly by the Atomic Energy Establishment at Winfrith (now called the Winfrith Technology Centre), Windscale Laboratory and Ove Arup and Partners. The work involved the investigation of the design of large transport containers for intermediate level reactor decommissioning waste, ie waste which requires shielding, and is aimed at European requirements (ie for both LWR and gas cooled reactors). It proposes a design methodology for such containers covering the whole lifetime of a waste disposal package. The design methodology presented takes account of various relevant constraints. Both large self shielded and returnable shielded concepts were developed. The work was generic, rather than specific; the results obtained, and the lessons learned, remain to be applied in practice

Fission product monitoring of TRISO coated fuel for the advanced gas reactor-1 experiment

International Nuclear Information System (INIS)

Scates, Dawn M.; Hartwell, John K.; Walter, John B.; Drigert, Mark W.; Harp, Jason M.

2010-01-01

The US Department of Energy has embarked on a series of tests of TRISO coated particle reactor fuel intended for use in the Very High Temperature Reactor (VHTR) as part of the Advanced Gas Reactor (AGR) program. The AGR-1 TRISO fuel experiment, currently underway, is the first in a series of eight fuel tests planned for irradiation in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The AGR-1 experiment reached a peak compact averaged burnup of 9% FIMA with no known TRISO fuel particle failures in March 2008. The burnup goal for the majority of the fuel compacts is to have a compact averaged burnup greater than 18% FIMA and a minimum compact averaged burnup of 14% FIMA. At the INL the TRISO fuel in the AGR-1 experiment is closely monitored while it is being irradiated in the ATR. The effluent monitoring system used for the AGR-1 fuel is the Fission Product Monitoring System (FPMS). The FPMS is a valuable tool that provides near real-time data indicative of the AGR-1 test fuel performance and incorporates both high-purity germanium (HPGe) gamma-ray spectrometers and sodium iodide [NaI(Tl)] scintillation detector-based gross radiation monitors. To quantify the fuel performance, release-to-birth ratios (R/B's) of radioactive fission gases are computed. The gamma-ray spectra acquired by the AGR-1 FPMS are analyzed and used to determine the released activities of specific fission gases, while a dedicated detector provides near-real time count rate information. Isotopic build up and depletion calculations provide the associated isotopic birth rates. This paper highlights the features of the FPMS, encompassing the equipment, methods and measures that enable the calculation of the release-to-birth ratios. Some preliminary results from the AGR-1 experiment are also presented.

Operational and reliability experience with reactor instrumentation

International Nuclear Information System (INIS)

Dixon, F.; Gow, R.S.

1978-01-01

In the last 15 years the CEGB has experienced progressive plant development, integration and changes in operating regime through nine nuclear (gas-cooled reactor) power stations with corresponding instrumentation advances leading towards more refined centralized control. Operation and reliability experience with reactor instrumentation is reported in this paper with reference to the progressive changes related to the early magnox, late magnox and AGR periods. Data on instrumentation reliability in terms of reactor forced outages are presented and show that the instrumentation contributions to loss of generating plant availability are small. Reactor safety circuits, neutron flux and temperature measurements, gas analysis and vibration monitoring are discussed. In reviewing the reactor instrumentation the emphasis is on reporting recent experience, particularly on AGR equipment, but overall performance and changes to magnox equipment are included so that some appreciation can be obtained of instrumentation requirements with respect to plant lifetimes. (author)

Thermal reactor strategy

International Nuclear Information System (INIS)

1981-01-01

This statement sets down briefly the CEGB's views on the requirement for nuclear power and outlines current progress in the implementation of the CEGB's thermal reactor strategy. The programme is traced historically, together with statements of Government policy. The place of Magnox, AGR, SGHWR, PWR and fast breeder reactors is discussed. Advantages and problems associated with the various types are outlined. (U.K.)

Manufacture of steam generator units and components for the AGR power stations at Heysham II and Torness

International Nuclear Information System (INIS)

Glasgow, J.R.; Parkin, K.

1984-01-01

The current AGR Steam Generator is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley B/Hunterston B AGR power stations. In this paper a brief outline of the evolution of the steam generator design from the earlier gas cooled reactor stations is presented. A description of the main items of fabrication development is given. The production facilities for the manufacture of the units are described. Reference is also made to some of the work on associated components. The early experience on the construction site of installation of the steam generators is briefly outlined. (author)

Manufacture of steam generator units and components for the AGR power stations at Heysham II and Torness

Energy Technology Data Exchange (ETDEWEB)

Glasgow, J R; Parkin, K [N.E.I. Nuclear Systems Ltd., Gateshead, Tyne and Wear (United Kingdom)

1984-07-01

The current AGR Steam Generator is a development of the successful once-through units supplied for the Oldbury Magnox and Hinkley B/Hunterston B AGR power stations. In this paper a brief outline of the evolution of the steam generator design from the earlier gas cooled reactor stations is presented. A description of the main items of fabrication development is given. The production facilities for the manufacture of the units are described. Reference is also made to some of the work on associated components. The early experience on the construction site of installation of the steam generators is briefly outlined. (author)

The development of direct core monitoring in Nuclear Electric plc

International Nuclear Information System (INIS)

Curtis, R.F.; Jones, S. Reed, J.; Wickham, A.J.

1996-01-01

Monitoring of graphite behaviour in Nuclear Electric Magnox and AGR reactors is necessary to support operating safety cases and to ensure that reactor operation is optimized to sustain the necessary core integrity for the economic life of the reactors. The monitoring programme combines studies for pre-characterized ''installed'' samples with studies on samples trepanned from within the cores and also with studies of core and channel geometry using specially designed equipment. Nuclear Electric has two trepanning machines originally designed for Magnox-reactor work which have been used for a substantial programme over many years. They have recently been upgraded to improve sampling speed, safety and versatility - the last being demonstrated by their adaptation for a recently-won contract associated with decommissioning the Windscale piles. Radiological hazards perceived when the AGR trepanning system was designed resulted in very cumbersome equipment. This has worked well but has been inconvenient in operation. The development of a smaller and improved system for deploying the equipment is now reported. Channel dimension monitoring equipment is discussed in detail with examples of data recovered from both Magnox and AGR cores. A resolution of ± 2 of arc (tilt) and ± 0.01 mm change in diameter in attainable. It is also theoretically possible to establish brick stresses by measuring geometry changes which result from trepanning. Current development work on a revolving scanning laser rangefinder which will enable the measurement of diameters to a resolution of 0.001 mm will also be discussed. This paper also discusses non-destructive techniques for crack detection employing ultrasound or resistance networks, the use of special manipulators to deliver inspection and repair equipment and recent developments to install displacement monitors in peripheral regions of the cores, to aid the understanding of the interaction of the restraint system with the core - the region

Two-reactor solution spells kiss of death for the SGHWR option

International Nuclear Information System (INIS)

Butler, P.

1977-01-01

The main points from the National Nuclear Corporation's assessment of thermal reactors are summarised. Three systems SGHWR, AGR, and PWR were examined. The NNC suggests extending the AGR programme whilst at the same time developing a PWR. (U.K.)

Neutronic of heterogenous gas cooled reactors

International Nuclear Information System (INIS)

Maturana, Roberto Hernan

2008-01-01

At present, one of the main technical features of the advanced gas cooled reactor under development is its fuel element concept, which implies a neutronic homogeneous design, thus requiring higher enrichment compared with present commercial nuclear power plants.In this work a neutronic heterogeneous gas cooled reactor design is analyzed by studying the neutronic design of the Advanced Gas cooled Reactor (AGR), a low enrichment, gas cooled and graphite moderated nuclear power plant.A search of merit figures (some neutronic parameter, characteristic dimension, or a mixture of both) which are important and have been optimized during the reactor design stage is been done, to aim to comprise how a gas heterogeneous reactor is been design, given that semi-infinity arrangement criteria of rods in LWRs and clusters in HWRs can t be applied for a solid moderator and a gas refrigerator.The WIMS code for neutronic cell calculations is been utilized to model the AGR fuel cell and to calculate neutronic parameters such as the multiplication factor and the pick factor, as function of the fuel burnup.Also calculation is been done for various nucleus characteristic dimensions values (fuel pin radius, fuel channel pitch) and neutronic parameters (such as fuel enrichment), around the design established parameters values.A fuel cycle cost analysis is carried out according to the reactor in study, and the enrichment effect over it is been studied.Finally, a thermal stability analysis is been done, in subcritical condition and at power level, to study this reactor characteristic reactivity coefficients.Present results shows (considering the approximation used) a first set of neutronic design figures of merit consistent with the AGR design. [es

Data Compilation for AGR-1 Baseline Coated Particle Composite LEU01-46T

International Nuclear Information System (INIS)

Hunn, John D.; Lowden, Richard Andrew

2006-01-01

This document is a compilation of characterization data for the AGR-1 baseline coated particle composite LEU01-46T, a composite of four batches of TRISO-coated 350 (micro)m 19.7% low enrichment uranium oxide/uranium carbide kernels (LEUCO). The AGR-1 TRISO-coated particles consist of a spherical kernel coated with a ∼ 50% dense carbon buffer layer (100 (micro)m nominal thickness) followed by a dense inner pyrocarbonlayer (40 (micro)m nominal thickness) followed by a SiC layer (35 (micro)m nominal thickness) followed by another dense outer pyrocarbon layer (40 (micro)m nominal thickness). The coated particles, were produced by ORNL for the Advanced Gas Reactor Fuel Development and Qualification (AGR) program to be put into compacts for insertion in the first irradiation test capsule, AGR-1. The kernels were obtained from BWXT and identified as composite (G73D-20-69302). The BWXT kernel lot G73D-20-69302 was riffled into sublots for characterization and coating by ORNL and identified as LEU01-?? (where ?? is a series of integers beginning with 01). Additional particle batches were coated with only buffer or buffer plus inner pyrocarbon (IPyC) layers using similar process conditions as used for the full TRISO batches comprising the LEU01-46T composite. These batches were fabricated in order to qualify that the process conditions used for buffer and IPyC would produce acceptable densities, as described in sections 8 and 9. These qualifying batches used 350 (micro)m natural uranium oxide/uranium carbide kernels (NUCO). The kernels were obtained from BWXT and identified as composite G73B-NU-69300. The use of NUCO surrogate kernels is not expected to significantly effect the densities of the buffer and IPyC coatings. Confirmatory batches using LEUCO kernels from G73D-20-69302 were coated and characterized to verify this assumption. The AGR-1 Fuel Product Specification and Characterization Guidance (INL EDF-4380, Rev. 6) provides the requirements necessary for acceptance

For sale: 7 AGR stations and a brand new PWR

International Nuclear Information System (INIS)

Anon.

1995-01-01

Britain's seven AGR stations and the Sizewell B PWR will pass to private ownership under the UK government's plan to privatise the two nuclear generators, Nuclear Electric and Scottish Nuclear, sometime next year. Under the new set-up, the two generators will become operating subsidiaries of a holding company which will be headquartered in Scotland. The companies' ageing Magnox gas-cooled reactors will remain in a separate public sector company before being transferred to British Nuclear Fuels (BNFL) at the time of privatisation. (author)

Windscale inquiry. A selected list of material based on the DOE/DTp library

Energy Technology Data Exchange (ETDEWEB)

Lambert, C M [comp.

1981-01-01

The nuclear debate, far from being concluded by the Windscale decision, was in fact opened up and its scope widened to take into account the political, international, environmental and social issues involved. This debate continues and the selection of literature presented here aims to illustrate all aspects of the Inquiry and its implications. The material is presented in two main sections. Section A is concerned with the Inquiry itself: the proceedings, the report and the government's decision. Section B presents a selection of the literature and debate that resulted.

X-ray Analysis of Defects and Anomalies in AGR-5/6/7 TRISO Particles

Energy Technology Data Exchange (ETDEWEB)

Helmreich, Grant W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Hunn, John D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Skitt, Darren J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dyer, John A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Schumacher, Austin T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-06-01

Coated particle fuel batches J52O-16-93164, 93165, 93166, 93168, 93169, 93170, and 93172 were produced by Babcock and Wilcox Technologies (BWXT) for possible selection as fuel for the Advanced Gas Reactor Fuel Development and Qualification (AGR) Program’s AGR-5/6/7 irradiation test in the Idaho National Laboratory (INL) Advanced Test Reactor (ATR), or may be used for other tests. Each batch was coated in a 150-mm-diameter production-scale fluidized-bed chemical vapor deposition (CVD) furnace. Tristructural isotropic (TRISO) coatings were deposited on 425-μm-nominal-diameter spherical kernels from BWXT lot J52R-16-69317 containing a mixture of 15.4%-enriched uranium carbide and uranium oxide (UCO), with the exception of Batch 93164, which used similar kernels from BWXT lot J52L-16-69316. The TRISO-coatings consisted of a ~50% dense carbon buffer layer with 100-μmnominal thickness, a dense inner pyrolytic carbon (IPyC) layer with 40-μm-nominal thickness, a silicon carbide (SiC) layer with 35-μm-nominal thickness, and a dense outer pyrolytic carbon (OPyC) layer with 40-μm-nominal thickness. Each coated particle batch was sieved to upgrade the particles by removing over-sized and under-sized material, and the upgraded batch was designated by appending the letter A to the end of the batch number (e.g., 93164A). Secondary upgrading by sieving was performed on the upgraded batches to remove specific anomalies identified during analysis for Defective IPyC, and the upgraded batches were designated by appending the letter B to the end of the batch number (e.g., 93165B). Following this secondary upgrading, coated particle composite J52R-16-98005 was produced by BWXT as fuel for the AGR Program’s AGR-5/6/7 irradiation test in the INL ATR. This composite was comprised of coated particle fuel batches J52O-16-93165B, 93168B, 93169B, and 93170B.

Mechanical Properties of Advanced Gas-Cooled Reactor Stainless Steel Cladding After Irradiation

Science.gov (United States)

Degueldre, Claude; Fahy, James; Kolosov, Oleg; Wilbraham, Richard J.; Döbeli, Max; Renevier, Nathalie; Ball, Jonathan; Ritter, Stefan

2018-05-01

The production of helium bubbles in advanced gas-cooled reactor (AGR) cladding could represent a significant hazard for both the mechanical stability and long-term storage of such materials. However, the high radioactivity of AGR cladding after operation presents a significant barrier to the scientific study of the mechanical properties of helium incorporation, said cladding typically being analyzed in industrial hot cells. An alternative non-active approach is to implant He2+ into unused AGR cladding material via an accelerator. Here, a feasibility study of such a process, using sequential implantations of helium in AGR cladding steel with decreasing energy is carried out to mimic the buildup of He (e.g., 50 appm) that would occur for in-reactor AGR clad in layers of the order of 10 µm in depth, is described. The implanted sample is subsequently analyzed by scanning electron microscopy, nanoindentation, atomic force and ultrasonic force microscopies. As expected, the irradiated zones were affected by implantation damage (steel cladding is retained despite He2+ implantation.

Assessment of the radiological impact of the Windscale reactor fire, October 1957. Addendum to report NRPB R135

Energy Technology Data Exchange (ETDEWEB)

Crick, M J; Linsley, G S

1983-01-01

The assessment described has involved a review of previously unpublished data, in order to establish the quantities of nuclides released from materials undergoing irradiation in the pile at the time of the fire. Of these additional nuclides, only polonium-210 has been shown to make a significant contribution to the estimate of the collective effective dose equivalent to the population from the Windscale fire. The previous estimate of 1.2 x 10/sup 3/ man Sv for the collective effective dose equivalent commitment to the population of the UK and Northern Europe has been increased by 67% to 2.0 x 10/sup 3/ man Sv. This change is within the range of uncertainty of the original estimate. The influence of the addition on the theoretical estimate of the upper limit of possible health effects is discussed in this addendum and its foreword. With the inclusion of the additional nuclides, the inhalation pathway has become the overall largest contributor to this population dose, followed by the milk ingestion pathway; the largest nuclide contribution comes from iodine-131, followed by polonium-210. Some perspective may be provided on the contribution due to polonium-210 by noting that it is approximately one-tenth of that arising annually due to naturally occurring polonium-210, and less than one-hundredth of that due annually to the total natural background radiation.

Determination of the Quantity of I-135 Released from the AGR Experiment Series

International Nuclear Information System (INIS)

Scates, Dawn M.; Walter, John B.; Reber, Edward L.; Sterbentz, James W.; Petti, David A.

2014-01-01

A series of three Advanced Gas Reactor (AGR) experiments have been conducted in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL). From 2006 through 2014, these experiments supported the development and qualification of the new U.S. tri-structural isotropic (TRISO) particle fuel for Very High Temperature Reactors (VHTR). Each AGR experiment consisted of multiple fueled capsules, each plumbed for independent temperature control using a mix of helium and neon gases. The gas leaving a capsule was routed to individual Fission Product Monitor (FPM) detectors. For intact fuel particles, the TRISO particle coatings provide a substantial barrier to fission product release. However, particles with failed coatings, whether because of a minute percentage of initially defective particles, those which fail during irradiation, or those designed-to-fail (DTF) particles, can release fission products to the flowing gas stream. Because reactive fission product elements like iodine and cesium quickly deposit on cooler capsule components and piping structures as the effluent gas leaves the reactor core, only the noble fission gas isotopes of Kr and Xe tend to reach FPM detectors. The FPM system utilizes High Purity Germanium (HPGe) detectors coupled with a thallium activated sodium iodide NaI(Tl) scintillator. The germanium detector provides individual isotopic information, while the NaI(Tl) scintillator is used as a gross count rate meter. During irradiation, the "1"3"5"mXe concentration reaching the FPM detectors is from both direct fission and by decay of the accumulated "1"3"5I. About ~2.5 hours after irradiation (ten 15.3 minute "1"3"5mXe half-lives) the directly produced "1"3"5"mXe has decayed and only the longer lived "1"3"5I remains as a source. Decay systematics dictate that "1"3"5"mXe will be in secular equilibrium with its "1"3"5I parent, such that it’s production rate very nearly equals the decay rate of the parent, and its concentration in the flowing

Project accent: graphite irradiated creep in a materials test reactor

International Nuclear Information System (INIS)

Brooking, M.

2014-01-01

Atkins manages a pioneering programme of irradiation experiments for EDF Energy. One of these projects is Project ACCENT, designed to obtain evidence of a beneficial physical property of the graphite, which may extend the life of the Advanced Gas-cooled Reactors (AGRs). The project team combines the in-house experience of EDF Energy with two supplier organisations (providing the material test reactors and testing facilities) and supporting consultancies (Atkins and an independent technical expert). This paper describes: - Brief summary of the Project; - Discussion of the challenges faced by the Project; and - Conclusion elaborating on the aims of the Project. These challenging experiments use bespoke technology and both un-irradiated (virgin) and irradiated AGR graphite. The results will help to better understand graphite irradiation-induced creep (or stress modified dimensional change) properties and therefore more accurately determine lifetime and safe operating envelopes of the AGRs. The first round of irradiation has been completed, with a second round about to commence. This is a key step to realising the full lifetime ambition for AGRs, demonstrating the relaxation of stresses within the graphite bricks. (authors)

Measurement techniques for AGR circulators in a full-density rig

International Nuclear Information System (INIS)

Watson, I.; Wilson, R.R.

1977-01-01

Safety and reliability are the most important factors of a nuclear power plant. This applies in particular to the circulators used to drive the high-density CO 2 around the reactor core and boiler circuits. Under operating conditions, very high sound-pressure levels are generated which could excite components and cause possible fatigue failures. Failures of this type were experienced on the original axial blowers for the Hinkley 'A' Magnox reactor and, following this, a stringent test plan was specified for the AGR circulators. The present paper describes some of the techniques used to measure strain, sound and vibration on circulators in a full-density rig. This rig reproduces the actual reactor working conditions of 300 0 C and 4.1 MN m -2 with gas velocities up to 120 m s -1 . Under these conditions sound-pressure levels of up to 172 dB are generated. This programme of circulator testing has continued for the past 10 years. During this period many obstacles and difficulties were encountered. Some of these problems, together with the solutions found, are discussed. (author)

Alpha-emitting nuclides in commercial fish species caught in the vicinity of Windscale, United Kingdom, and their radiological significance to man

International Nuclear Information System (INIS)

Pentreath, R.J.; Lovett, M.B.; Harvey, B.R.; Ibbett, R.D.

1979-01-01

The concentrations of a number of alpha-emitting nuclides have been determined in the tissues of several commercial fish species caught in the vicinity of the fuel reprocessing plant at Windscale. All tissues analysed were found to contain 238 Pu, sup(239+240)Pu and 241 Am, but 242 Cm and 244 Cm could only be reliably detected in the liver samples of some fish. Fish of the same species, but taken from the North Sea, have also been analysed for some naturally occurring alpha-emitting nuclides. Whereas uranium ( 238 U) and thorium ( 232 Th) could be detected in bone samples of fish, neither could be reliably detected in samples of muscle: in contrast, 210 Po was readily detected in samples of liver, muscle and bone. Commercial fish fillets from the Irish Sea, including the Windscale area, are also routinely monitored for alpha-emitting nuclides, and their radiological significance to man is briefly discussed. Comments are also made on the significance of the naturally occurring nuclides. (author)

Comparison of silver release predictions using PARFUME with results from the AGR-2 irradiation experiment

Energy Technology Data Exchange (ETDEWEB)

Collin, Blaise P.; Demkowicz, Paul A.; Baldwin, Charles A.; Harp, Jason M.; Hunn, John D.

2016-11-01

The PARFUME (PARticle FUel ModEl) code was used to predict silver release from tristructural isotropic (TRISO) coated fuel particles and compacts during the second irradiation experiment (AGR-2) of the Advanced Gas Reactor Fuel Development and Qualification program. The PARFUME model for the AGR-2 experiment used the fuel compact volume average temperature for each of the 559 days of irradiation to calculate the release of fission product silver from a representative particle for a select number of AGR-2 compacts and individual fuel particles containing either mixed uranium carbide/oxide (UCO) or 100% uranium dioxide (UO2) kernels. Post-irradiation examination (PIE) measurements were performed to provide data on release of silver from these compacts and individual fuel particles. The available experimental fractional releases of silver were compared to their corresponding PARFUME predictions. Preliminary comparisons show that PARFUME under-predicts the PIE results in UCO compacts and is in reasonable agreement with experimental data for UO2 compacts. The accuracy of PARFUME predictions is impacted by the code limitations in the modeling of the temporal and spatial distributions of the temperature across the compacts. Nevertheless, the comparisons on silver release lie within the same order of magnitude.

Emission of fission products and other activities during the accident to Windscale Pile no. 1 in October 1957

International Nuclear Information System (INIS)

Chamberlain, A.C.

1981-07-01

Information on the release of activity from Windscale during the accident of October 1957 is reviewed, and some previously unpublished data are given. The activities of 131 I released to atmosphere, retained on the pile filters and washed out of the pile are compared with the activity in the channels involved in the fire. The information on the physical form of the released activity is summarised. (author)

AGR-2 Final Data Qualification Report for U.S. Capsules - ATR Cycles 147A Through 154B

Energy Technology Data Exchange (ETDEWEB)

Pham, Binh T. [Idaho National Lab. (INL), Idaho Falls, ID (United States). Very High-Temperature Reactor Technology Development Office; Einerson, Jeffrey J. [Idaho National Lab. (INL), Idaho Falls, ID (United States). Very High-Temperature Reactor Technology Development Office

2014-07-01

This report provides the data qualification status of AGR-2 fuel irradiation experimental data in four U.S. capsules from all 15 Advanced Test Reactor (ATR) Cycles 147A, 148A, 148B, 149A, 149B, 150A, 150B, 151A, 151B, 152A, 152B, 153A, 153B, 154A, and 154B, as recorded in the Nuclear Data Management and Analysis System (NDMAS). Thus, this report covers data qualification status for the entire AGR-2 irradiation and will replace four previously issued AGR-2 data qualification reports (e.g., INL/EXT-11-22798, INL/EXT-12-26184, INL/EXT-13-29701, and INL/EXT-13-30750). During AGR-2 irradiation, two cycles, 152A and 153A, occurred when the ATR core was briefly at low power, so AGR-2 irradiation data are not used for physics and thermal calculations. Also, two cycles, 150A and 153B, are Power Axial Locator Mechanism (PALM) cycles when the ATR power is higher than during normal cycles. During the first PALM cycle, 150A, the experiment was temporarily moved from the B-12 location to the ATR water canal and during the second PALM cycle, 153B, the experiment was temporarily moved from the B-12 location to the I-24 location to avoid being overheated. During the “Outage” cycle, 153A, seven flow meters were installed downstream from seven Fission Product Monitoring System (FPMS) monitors to measure flows from the monitors and these data are included in the NDMAS database.

Ecological and toxicological aspects of the partial meltdown of the Chernobyl nuclear power plant reactor

Science.gov (United States)

Eisler, Ronald; Hoffman, David J.; Rattner, Barnett A.; Burton, G. Allen; Cairns, John

1995-01-01

the partial meltdown of the 1000-MW reactor at Chernobyl, Ukraine, on April 26, 1986, released large amounts of radiocesium and other radionuclides into the environment, causing widespread radioactive contamination of Europe and the former Soviet Union.1-7 At least 3,000,000 trillion becquerels (TBq) were released from the fuel during the accident (Table 24.1), dwarfing, by orders of magnitude, radiation released from other highly publicized reactor accidents at Windscale (U.K.) and three-Mile Island (U.S.)3,8 The Chernobyl accident happened while a test was being conducted during a normal scheduled shutdown and is attributed mainly to human error.3

Nuclear reactor types

International Nuclear Information System (INIS)

Jones, P.M.S.

1987-01-01

The characteristics of different reactor types designed to exploit controlled fission reactions are explained. Reactors vary from low power research devices to high power devices especially designed to produce heat, either for direct use or to produce steam to drive turbines to generate electricity or propel ships. A general outline of basic reactors (thermal and fast) is given and then the different designs considered. The first are gas cooled, including the Magnox reactors (a list of UK Magnox stations and reactor performance is given), advanced gas cooled reactors (a list of UK AGRs is given) and the high temperature reactor. Light water cooled reactors (pressurized water [PWR] and boiling water [BWR] reactors) are considered next. Heavy water reactors are explained and listed. The pressurized heavy water reactors (including CANDU type reactors), boiling light water, steam generating heavy water reactors and gas cooled heavy water reactors all come into this category. Fast reactors (liquid metal fast breeder reactors and gas cooled fast reactors) and then water-cooled graphite-moderated reactors (RBMK) (the type at Chernobyl-4) are discussed. (U.K.)

The United Kingdom

International Nuclear Information System (INIS)

Jones, P.M.S.

1987-01-01

The history of nuclear development in the United Kingdom is traced, together with the factors (eg electricity demand, fossil fuel prices, political policy) that have influenced policy choices. Many of the research establishments and the fissile material production plants were established in the late 1940s. In these early years the civil and military development programmes were not separate. The initial growth period was in the 1950s when the plan was to build twelve reactors in three groups of four over ten years. The first were to be Magnox type reactors. This was trebled in 1957 and the advanced gas cooled reactor was developed. The Windscale fire in 1957 affected confidence in the nuclear programme. However, five AGR twin-reactor stations were ordered in 1964. These ran into construction problems and delay and it was not until 1980 that more new units were contemplated. The plan then was to build a pressurized water reactor at Sizewell-B. A delay to allow for the public inquiry put back the start of this until 1987 with commissioning planned for 1994. A list of the UK nuclear power stations is given and their operating performance discussed. The present situation and future prospects for nuclear power are reviewed. (U.K.)

United Kingdom and USSR reactor types

International Nuclear Information System (INIS)

Lewins, Jeffery

1988-01-01

The features of the RBMK reactor operated at Chernobyl are compared with reactor types pertinent to the UK. The UK reactors covered are in three classes: the commercial reactors now built and operated or in commission (Magnox and Advanced Gas-cooled Reactor (AGR)); the prototype Steam Generating Heavy Water Reactor (SGHWR) and Prototype Fast Reactor (PFR) that have comparable performance to commercial reactors; and the proposed Pressurised Water Reactor (PWR) or Sizewell 'B' design which, it will be recollected, is different in detail from PWRs built elsewhere. We do not include research and test reactors nor the Royal Navy PWRs. The appendices explain resonances, Doppler and Xenon effects, the reactor physics of Chernobyl and positive void coefficients all of which are relevant to the comparisons. (author)

Remote inspection manipulators for AGR II: Babcock Power's interstitial manipulator

International Nuclear Information System (INIS)

Whyley, S.R.

1985-01-01

The interstitial manipulator has been designed and built by Babcock Power for the remote visual inspection of AGR II reactors at Heysham and Torness. Its five drives are operated from a console local to the manipulator on the pile cap, or from a similar console located remotely. The need to operate from an interstitial ISI standpipe has restricted the size of the components entering the reactor, and this has consequently provided the major design constraint. A detailed structural assessment of the manipulator was carried out to demonstrate the ability to operate with payloads in excess of the largest camera weight of 13.6 kg. The manipulator finite element model was also used to determine static deflections, and, as a consequence, has provided data from which the control system is able to predict accurately the camera's position. Other computer aided design techniques have enabled the step by step sequences of manipulator deployment, in the restricted space available, to be successfully demonstrated. (author)

AgrAbility Project

Science.gov (United States)

... Cordless Ratchet Wrench ClampTite Wire Clamping Tool iBlue Smart Gate/Door Opener Full Toolbox AT Database Extranet ... in-person NTW - March 19-22, Portland, Maine House and Senate Appropriations Committees recommend restoring AgrAbility funding... ...

Irradiation performance of AGR-1 high temperature reactor fuel

Energy Technology Data Exchange (ETDEWEB)

Demkowicz, Paul A., E-mail: paul.demkowicz@inl.gov [Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415-6188 (United States); Hunn, John D. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831-6093 (United States); Ploger, Scott A. [Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415-6188 (United States); Morris, Robert N.; Baldwin, Charles A. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831-6093 (United States); Harp, Jason M.; Winston, Philip L. [Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415-6188 (United States); Gerczak, Tyler J. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831-6093 (United States); Rooyen, Isabella J. van [Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415-6188 (United States); Montgomery, Fred C.; Silva, Chinthaka M. [Oak Ridge National Laboratory, PO Box 2008, Oak Ridge, TN 37831-6093 (United States)

2016-09-15

Highlights: • Post-irradiation examination was performed on AGR-1 coated particle fuel. • Cesium release from the particles was very low in the absence of failed SiC layers. • Silver release was often substantial, and varied considerably with temperature. • Buffer and IPyC layers were found to play a key role in TRISO coating behavior. • Fission products palladium and silver were found in the SiC layer of particles. - Abstract: The AGR-1 experiment contained 72 low-enriched uranium oxide/uranium carbide TRISO coated particle fuel compacts in six capsules irradiated to burnups of 11.2 to 19.6% FIMA, with zero TRISO coating failures detected during the irradiation. The irradiation performance of the fuel including the extent of fission product release and the evolution of kernel and coating microstructures was evaluated based on detailed examination of the irradiation capsules, the fuel compacts, and individual particles. Fractional release of {sup 110m}Ag from the fuel compacts was often significant, with capsule-average values ranging from 0.01 to 0.38. Analysis of silver release from individual compacts indicated that it was primarily dependent on fuel temperature history. Europium and strontium were released in small amounts through intact coatings, but were found to be significantly retained in the outer pyrocarbon and compact matrix. The capsule-average fractional release from the compacts was 1 × 10{sup −4} to 5 × 10{sup −4} for {sup 154}Eu and 8 × 10{sup −7} to 3 × 10{sup −5} for {sup 90}Sr. The average {sup 134}Cs fractional release from compacts was <3 × 10{sup −6} when all particles maintained intact SiC. An estimated four particles out of 2.98 × 10{sup 5} in the experiment experienced partial cesium release due to SiC failure during the irradiation, driving {sup 134}Cs fractional release in two capsules to approximately 10{sup −5}. Identification and characterization of these particles has provided unprecedented insight into

HIGH-TEMPERATURE SAFETY TESTING OF IRRADIATED AGR-1 TRISO FUEL

Energy Technology Data Exchange (ETDEWEB)

Stempien, John D.; Demkowicz, Paul A.; Reber, Edward L.; Chrisensen, Cad L.

2016-11-01

High-Temperature Safety Testing of Irradiated AGR-1 TRISO Fuel John D. Stempien, Paul A. Demkowicz, Edward L. Reber, and Cad L. Christensen Idaho National Laboratory, P.O. Box 1625 Idaho Falls, ID 83415, USA Corresponding Author: john.stempien@inl.gov, +1-208-526-8410 Two new safety tests of irradiated tristructural isotropic (TRISO) coated particle fuel have been completed in the Fuel Accident Condition Simulator (FACS) furnace at the Idaho National Laboratory (INL). In the first test, three fuel compacts from the first Advanced Gas Reactor irradiation experiment (AGR-1) were simultaneously heated in the FACS furnace. Prior to safety testing, each compact was irradiated in the Advanced Test Reactor to a burnup of approximately 15 % fissions per initial metal atom (FIMA), a fast fluence of 3×1025 n/m2 (E > 0.18 MeV), and a time-average volume-average (TAVA) irradiation temperature of about 1020 °C. In order to simulate a core-conduction cool-down event, a temperature-versus-time profile having a peak temperature of 1700 °C was programmed into the FACS furnace controllers. Gaseous fission products (i.e., Kr-85) were carried to the Fission Gas Monitoring System (FGMS) by a helium sweep gas and captured in cold traps featuring online gamma counting. By the end of the test, a total of 3.9% of an average particle’s inventory of Kr-85 was detected in the FGMS traps. Such a low Kr-85 activity indicates that no TRISO failures (failure of all three TRISO layers) occurred during the test. If released from the compacts, condensable fission products (e.g., Ag-110m, Cs-134, Cs-137, Eu-154, Eu-155, and Sr-90) were collected on condensation plates fitted to the end of the cold finger in the FACS furnace. These condensation plates were then analyzed for fission products. In the second test, five loose UCO fuel kernels, obtained from deconsolidated particles from an irradiated AGR-1 compact, were heated in the FACS furnace to a peak temperature of 1600 °C. This test had two

The application of external vibration monitoring to reactors with concrete pressure vessels

International Nuclear Information System (INIS)

Hammill, W.J.

1979-01-01

The application of external vibration monitoring techniques to advanced gas cooled reactors (AGR) which have concrete pressure vessels is considered. A monitoring system for a particular AGR coolant circuit structure is developed, whose primary objective is to detect impacting of two components, although the detection of forced vibration response is also considered. Experimental results from instrumented components in the reactor and data from rig tests on full size units have been used together with a mathematical model of some elements of the transmission path in order to establish its dynamic characteristics and relate internal component vibration to externally measured signals. The application of external vibration monitoring to the external detection of the forced vibration response of an internal reactor assembly and the remote monitoring of circulator sound output is discussed. (author)

The fast breeder reactor

International Nuclear Information System (INIS)

Collier, J.

1990-01-01

The arguments for and against the fast breeder reactor are debated. The case for the fast reactor is that the world energy demand will increase due to increasing population over the next forty years and that the damage to the global environment from burning fossil fuels which contribute to the greenhouse effect. Nuclear fission is the only large scale energy source which can achieve a cut in the use of carbon based fuels although energy conservation and renewable sources will also be important. Fast reactors produce more energy from uranium than other types of (thermal) reactors such as AGRs and PWRs. Fast reactors would be important from about 2020 onwards especially as by then many thermal reactors will need to be replaced. Fast reactors are also safer than normal reactors. The arguments against fast reactors are largely economic. The cost, especially the capital cost is very high. The viability of the technology is also questioned. (UK)

Seminar on Comparative assessment of the environmental impact of radionuclides released during three major nuclear accidents: Kyshtym, Windscale, Chernobyl. Vol. 1

International Nuclear Information System (INIS)

1991-01-01

These proceedings of seminar on comparative assessment of the environmental impact of radionuclides released during three major nuclear accidents (Kyshtym, Windscale, Chernobyl) are divided into 5 parts bearing on: part 1: accident source terms; part 2: atmospheric dispersion, resuspension, chemical and physical forms of contamination; part 3: environmental contamination and transfer; part 4: radiological implications for man and his environment; part 5: countermeasures

Impact on burnup performance of coated particle fuel design in pebble bed reactor with ROX fuel

International Nuclear Information System (INIS)

Ho, Hai Quan; Obara, Toru

2015-01-01

The pebble bed reactor (PBR), a kind of high-temperature gas-cooled reactor (HTGR), is expected to be among the next generation of nuclear reactors as it has excellent passive safety features, as well as online refueling and high thermal efficiency. Rock-like oxide (ROX) fuel has been studied at the Japan Atomic Energy Agency (JAEA) as a new once-through type fuel concept. Rock-like oxide used as fuel in a PBR can be expected to achieve high burnup and improve chemical stabilities. In the once-through fuel concept, the main challenge is to achieve as high a burnup as possible without failure of the spent fuel. The purpose of this study was to investigate the impact on burnup performance of different coated fuel particle (CFP) designs in a PBR with ROX fuel. In the study, the AGR-1 Coated Particle design and Deep-Burn Coated Particle design were used to make the burnup performance comparison. Criticality and core burnup calculations were performed by MCPBR code using the JENDL-4.0 library. Results at equilibrium showed that the two reactors utilizing AGR-1 Coated Particle and Deep-Burn Coated Particle designs could be critical with almost the same multiplication factor k eff . However, the power peaking factor and maximum power per fuel ball in the AGR-1 coated particle design was lower than that of Deep-Burn coated particle design. The AGR-1 design also showed an advantage in fissions per initial fissile atoms (FIFA); the AGR-1 coated particle design produced a higher FIFA than the Deep-Burn coated particle design. These results suggest that the difference in coated particle fuel design can have an effect on the burnup performance in ROX fuel. (author)

Saúde e mercado de trabalho no Brasil: diferenciais entre ocupados agrícolas e não agrícolas

Directory of Open Access Journals (Sweden)

Alexandre Gori Maia

2010-12-01

Full Text Available Este trabalho analisa as diferenças no estado de saúde entre e dentro dos grupos de ocupados agrícolas e não agrícolas no Brasil, utilizando medidas de autoavaliação do estado de saúde captadas no suplemento da PNAD (Pesquisa Nacional por Amostra de Domicílios de 2008. As análises baseiam-se na composição socioeconômica dos ocupados agrícolas e não agrícolas e nas estimativas de equações simultâneas para captar as relações não lineares entre saúde, renda e jornada de trabalho. Um dos pressupostos do trabalho é que a baixa prevalência de saudáveis entre os ocupados agrícolas estaria associada, sobretudo, à composição socioeconômica desse grupo, e não à maior insalubridade a que os ocupados das atividades agrícolas estariam submetidos em condições socioeconômicas semelhantes às dos não agrícolas. Analogamente, a desigualdade no estado de saúde seria menor entre os ocupados agrícolas devido aos hábitos mais homogêneos, não só no que se refere ao tipo de atividade, mas também em relação à qualidade de vida e ao acesso a uma série de itens de consumo, típico das localidades menos desenvolvidas onde as atividades agrícolas prevalecem.This paper analyzes differences of health conditions between and within agricultural and non-agricultural workers in Brazil. Self-reported health measures of the Health Supplement of Pesquisa Nacional por Amostra de Domicílios (PNAD, from 2008, are used. Results are based on the description of the socioeconomic characteristics of each group of employees and on estimates of a simultaneous equation to measure non-linear relations between health conditions, income and work hours. The main hypothesis is that the lower prevalence of workers with good health among agricultural workers is mainly due to socioeconomic characteristics of this group and not necessarily to higher insalubrious conditions that such workers would be submitted to in equivalent socioeconomic conditions

A formação de Licenciados em Ciências Agrícolas/Agrárias: o conhecimento e suas conexões

Directory of Open Access Journals (Sweden)

Marco Antonio de Moraes

2014-11-01

Full Text Available http://dx.doi.org/10.5902/1984644413683Este trabalho visa identificar os perfis de formação dos licenciados de Ciências Agrícolas/Agrárias e os objetivos dos cursos que formam estes profissionais no Brasil. Neste estudo exploratório, os dados foram coletados através da Internet no site do MEC e das Instituições de Ensino Superior. O perfil geralmente proposto na formação do professor em Ciências Agrícolas/Agrícolas é amplo, com atuação em diferentes campos das Ciências Agrárias com finalidades econômicas, mas com atenção às questões sócio-políticas e culturais presentes no meio rural brasileiro. Percebe-se a intenção de formar licenciados que atendam alguns aspectos ou demandas regionais e que estejam preparados para as questões da atualidade. Destaca-se a preocupação com o desenvolvimento de algumas competências importantes na formação do profissional que irá atuar na educação escolar.

Practical decommissioning experience with nuclear installations in the European Community

International Nuclear Information System (INIS)

Skupinski, E.

1992-01-01

Initiated by the Commission of the European Communities (CEC), this seminar was jointly organized by the AEA, BNFL and the CEC at Windermere and the sites of Windscale/Sellafield, where the former Windscale advanced gas-cooled reactor and the Windscale piles are currently being dismantled. The meeting aimed at gathering a limited number of European experts for the presentation and discussion of operations, results and conclusions on techniques and procedures currently applied in the dismantling of large scale nuclear installations in the European Community

The safety of the AGR

International Nuclear Information System (INIS)

Dale, G.C.; Bowerman, J.M.

1982-01-01

The publication is in 10 parts. Section 1 describes regulatory control of the nuclear industry in the UK and outlines the principal Acts of Parliament and international regulations currently in force in the licensing of nuclear power stations. Section 2 discusses the responsibilities laid on licensees of nuclear sites for ensuring the safety of their employees and members of the public. In Section 3, a comprehensive description of the Advanced Gas-cooled Reactor (AGR) system and its principal components is given. The safety features are described in Section 4. Radiological effects are described in Section 5. Section 6 explains how different types of radioactive wastes arise and describes their management and plans for their long-term disposal. Section 7 deals with the transportation of fuel and radioactive waste. Section 8 is devoted to fault conditions; the steps taken to ensure adequate protection against faults and the reliability of plant are described. Liaison with local communities is discussed in Section 9; the role of the Local Liaison Committees is described and details of emergency plans are given. The final section covers the decommissioning and dismantling of power stations after they have reached the end of their useful lives. (author)

An analysis of nuclear fuel burnup in the AGR-1 TRISO fuel experiment using gamma spectrometry, mass spectrometry, and computational simulation techniques

International Nuclear Information System (INIS)

Harp, Jason M.; Demkowicz, Paul A.; Winston, Philip L.; Sterbentz, James W.

2014-01-01

Highlights: • The burnup of irradiated AGR-1 TRISO fuel was analyzed using gamma spectrometry. • The burnup of irradiated AGR-1 TRISO fuel was also analyzed using mass spectrometry. • Agreement between experimental results and neutron physics simulations was excellent. - Abstract: AGR-1 was the first in a series of experiments designed to test US TRISO fuel under high temperature gas-cooled reactor irradiation conditions. This experiment was irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) and is currently undergoing post-irradiation examination (PIE) at INL and Oak Ridge National Laboratory. One component of the AGR-1 PIE is the experimental evaluation of the burnup of the fuel by two separate techniques. Gamma spectrometry was used to non-destructively evaluate the burnup of all 72 of the TRISO fuel compacts that comprised the AGR-1 experiment. Two methods for evaluating burnup by gamma spectrometry were developed, one based on the Cs-137 activity and the other based on the ratio of Cs-134 and Cs-137 activities. Burnup values determined from both methods compared well with the values predicted from simulations. The highest measured burnup was 20.1% FIMA (fissions per initial heavy metal atom) for the direct method and 20.0% FIMA for the ratio method (compared to 19.56% FIMA from simulations). An advantage of the ratio method is that the burnup of the cylindrical fuel compacts can be determined in small (2.5 mm) axial increments and an axial burnup profile can be produced. Destructive chemical analysis by inductively coupled mass spectrometry (ICP-MS) was then performed on selected compacts that were representative of the expected range of fuel burnups in the experiment to compare with the burnup values determined by gamma spectrometry. The compacts analyzed by mass spectrometry had a burnup range of 19.3% FIMA to 10.7% FIMA. The mass spectrometry evaluation of burnup for the four compacts agreed well with the gamma

Preparation for Future Defuelling and Decommissioning Works on EDF Energy's UK Fleet of Advanced Gas Cooled Reactors

International Nuclear Information System (INIS)

Bryers, John; Ashmead, Simon

2016-01-01

EDF Energy/Nuclear Generation is the owner and operator of 14 Advanced Gas cooled Reactors (AGR) and one Pressurised Water Reactor (PWR), on 8 nuclear stations in the UK. EDF Energy/Nuclear Generation is responsible for all the activities associated with the end of life of its nuclear installations: de-fuelling, decommissioning and waste management. As the first AGR is forecast to cease generation within 10 years, EDF Energy has started planning for the decommissioning. This paper covers: - broad outline of the technical strategy and arrangements for future de-fuelling and decommissioning works on the UK AGR fleet, - high level strategic drivers and alignment with wider UK nuclear policy, - overall programme of preparation and initial works, - technical approaches to be adopted during decommissioning. (authors)

Safety design features for current UK advanced gas-cooled reactors

Energy Technology Data Exchange (ETDEWEB)

Yellowlees, J. M.; Cobb, E. C. [Nuclear Power Co. (Risley) Ltd. (UK)

1981-01-15

The nuclear power stations planned for Heysham II and Torness will each have twin 660 MW(e) Advanced Gas-cooled Reactors (AGR) based on the design of those which have been operating at Hinkley Point 'B' and Hunterston 'B' since 1976. This paper has described the way in which the shutdown and cooling systems for the Heysham II and Torness AGRs have been selected in order to meet current UK safety requirements. Fault tree analyses have been used to identify the credible fault sequences, the probabilities of which have been calculated. By this means the relative importance of the various protective systems has been established and redundancy and reliability requirements identified. This systematic approach has led to a balanced design giving protection over the complete spectrum of fault sequences. Current safety requirements for thermal reactors in the UK and particular requirements in the design of the Heysham II and Torness reactors are discussed.

Safety design features for current UK advanced gas-cooled reactors

International Nuclear Information System (INIS)

Yellowlees, J.M.; Cobb, E.C.

1981-01-01

The nuclear power stations planned for Heysham II and Torness will each have twin 660 MW(e) Advanced Gas-cooled Reactors (AGR) based on the design of those which have been operating at Hinkley Point 'B' and Hunterston 'B' since 1976. This paper has described the way in which the shutdown and cooling systems for the Heysham II and Torness AGRs have been selected in order to meet current UK safety requirements. Fault tree analyses have been used to identify the credible fault sequences, the probabilities of which have been calculated. By this means the relative importance of the various protective systems has been established and redundancy and reliability requirements identified. This systematic approach has led to a balanced design giving protection over the complete spectrum of fault sequences. Current safety requirements for thermal reactors in the UK and particular requirements in the design of the Heysham II and Torness reactors are discussed

Mecanização Agrícola - Análise de aspectos de operacionalidade de máquinas agrícolas

OpenAIRE

Peça, José

2012-01-01

Este trabalho destina-se a apoiar a aprendizagem de estudantes do ramo das ciências agrárias sobre aspectos relevantes à operacionalidade das máquinas agrícolas. Utilização das equações de equilíbrio na previsão de esforços sobre os eixos de tractores com alfaias montadas e semi-montadas com vista a salvaguardar os limites técnicos, a estabilidade em declives e a qualidade do solo. Dada a importância que têm as operações de manuseamento de carga nas explorações agrícolas, é abordado o...

Acceptance Test Data for the AGR-5/6/7 Irradiation Test Fuel Composite Defective IPyC Fraction and Pyrocarbon Anisotropy

Energy Technology Data Exchange (ETDEWEB)

Helmreich, Grant W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Hunn, John D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Skitt, Darren J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dyer, John A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Schumacher, Austin T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-05-01

Coated particle composite J52R-16-98005 was produced by Babcock and Wilcox Technologies (BWXT) as fuel for the Advanced Gas Reactor Fuel Development and Qualification (AGR) Program’s AGR-5/6/7 irradiation test in the Idaho National Laboratory (INL) Advanced Test Reactor (ATR). This composite was comprised of four coated particle fuel batches J52O-16-93165B (26%), 93168B (26%), 93169B (24%), and 93170B (24%), chosen based on the Quality Control (QC) data acquired for each individual candidate AGR-5/6/7 batch. Each batch was coated in a 150-mm-diameter production-scale fluidized-bed chemical vapor deposition (CVD) furnace. Tristructural isotropic (TRISO) coatings were deposited on 425-μm-nominal-diameter spherical kernels from BWXT Lot J52R-16-69317 containing a mixture of 15.5%-enriched uranium carbide and uranium oxide (UCO). The TRISO coatings consisted of four consecutive CVD layers: a ~50% dense carbon buffer layer with 100-μm-nominal thickness, a dense inner pyrolytic carbon (IPyC) layer with 40-μm-nominal thickness, a silicon carbide (SiC) layer with 35-μm-nominal thickness, and a dense outer pyrolytic carbon (OPyC) layer with 40-μm-nominal thickness. The TRISO-coated particle batches were sieved to upgrade the particles by removing over-sized and under-sized material, and the upgraded batches were designated by appending the letter A to the end of the batch number (e.g., 93165A). Secondary upgrading by sieving was performed on the A-designated batches to remove particles with missing or very-thin buffer layers that were identified during previous analysis of the individual batches for defective IPyC, as reported in the acceptance test data report for the AGR-5/6/7 production batches [Hunn et al. 2017]. The additionally-upgraded batches were designated by appending the letter B to the end of the batch number (e.g., 93165B).

MEASUREMENTS MADE DURING THE COMMISSIONING OF THE WINDSCALE ADVANCED GAS- COOLED REACTOR (WAGR)

Energy Technology Data Exchange (ETDEWEB)

Gallie, R R

1963-06-15

Some measurements were made on the WAGR fuel in the APEX and HERO facilities in order to derive the loading pattern. The reactor was then loaded, and measurements of the excess reactivity were in good agreement with predictions. Other measurements made were control rod calibrations, reactivity worths of control rods, isothermal temperature coefficient, and pressure drops. (D.L.C.)

Field test and evaluation of the passive neutron coincidence collar for prototype fast reactor fuel subassemblies

International Nuclear Information System (INIS)

Menlove, H.O.; Keddar, A.

1982-08-01

The passive neutron Coincidence Collar, which was developed for the verification of plutonium content in fast reactor fuel subassemblies, has been field tested using Prototype Fast Reactor fuel. For passive applications, the system measures the 240 Pu-effective mass from the spontaneous fission rate, and in addition, a self-interrogation technique is used to determine the fissile content in the subassembly. Both the passive and active modes were evaluated at the Windscale Works in the United Kingdom. The results of the tests gave a standard deviation 0.75% for the passive count and 3 to 7% for the active measurement for a 1000-s counting time. The unit will be used in the future for the verification of plutonium in fresh fuel assemblies

AGR-5/6/7 LEUCO Kernel Fabrication Readiness Review

Energy Technology Data Exchange (ETDEWEB)

Marshall, Douglas W. [Idaho National Lab. (INL), Idaho Falls, ID (United States). Fuel Design and Development; Bailey, Kirk W. [Idaho National Lab. (INL), Idaho Falls, ID (United States). ART Quality Assurance Engineer

2015-02-01

In preparation for forming low-enriched uranium carbide/oxide (LEUCO) fuel kernels for the Advanced Gas Reactor (AGR) fuel development and qualification program, Idaho National Laboratory conducted an operational readiness review of the Babcock & Wilcox Nuclear Operations Group – Lynchburg (B&W NOG-L) procedures, processes, and equipment from January 14 – January 16, 2015. The readiness review focused on requirements taken from the American Society Mechanical Engineers (ASME) Nuclear Quality Assurance Standard (NQA-1-2008, 1a-2009), a recent occurrence at the B&W NOG-L facility related to preparation of acid-deficient uranyl nitrate solution (ADUN), and a relook at concerns noted in a previous review. Topic areas open for the review were communicated to B&W NOG-L in advance of the on-site visit to facilitate the collection of objective evidences attesting to the state of readiness.

The moderator's moderator

International Nuclear Information System (INIS)

Williamson, G.K.

1990-01-01

A brief account is given of the development of graphite moderators for Magnox and advanced gas cooled reactors. The accident at Windscale in 1957 brought to worldwide attention the importance of irradiation damage in graphite and the consequent storage of Wigner energy. In spite of the Windscale setback, preparations for the civil programme of Magnox reactors went ahead apace. Some of the background to the disastrous Dungeness B tender is presented. In spite of all the difficulties and uncertainties, the graphite in UK reactors has performed well. In all cases, as far as the author is aware, the behaviour of the graphite moderators will not prevent design life being achieved. (author)

AGR-2 Irradiated Test Train Preliminary Inspection and Disassembly First Look

Energy Technology Data Exchange (ETDEWEB)

Ploger, Scott [Idaho National Lab. (INL), Idaho Falls, ID (United States); Demkowciz, Paul [Idaho National Lab. (INL), Idaho Falls, ID (United States); Harp, Jason [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-05-01

The AGR 2 irradiation experiment began in June 2010 and was completed in October 2013. The test train was shipped to the Materials and Fuels Complex in July 2014 for post-irradiation examination (PIE). The first PIE activities included nondestructive examination of the test train, followed by disassembly of the test train and individual capsules and detailed inspection of the capsule contents, including the fuel compacts and their graphite fuel holders. Dimensional metrology was then performed on the compacts, graphite holders, and steel capsule shells. AGR 2 disassembly and metrology were performed with the same equipment used successfully on AGR 1 test train components. Gamma spectrometry of the intact test train gave a preliminary look at the condition of the interior components. No evidence of damage to compacts or graphite components was evident from the isotopic and gross gamma scans. Disassembly of the AGR 2 test train and its capsules was conducted rapidly and efficiently by employing techniques refined during the AGR 1 disassembly campaign. Only one major difficulty was encountered while separating the test train into capsules when thermocouples (of larger diameter than used in AGR 1) and gas lines jammed inside the through tubes of the upper capsules, which required new tooling for extraction. Disassembly of individual capsules was straightforward with only a few minor complications. On the whole, AGR 2 capsule structural components appeared less embrittled than their AGR 1 counterparts. Compacts from AGR 2 Capsules 2, 3, 5, and 6 were in very good condition upon removal. Only relatively minor damage or markings were visible using high resolution photographic inspection. Compact dimensional measurements indicated radial shrinkage between 0.8 to 1.7%, with the greatest shrinkage observed on Capsule 2 compacts that were irradiated at higher temperature. Length shrinkage ranged from 0.1 to 0.9%, with by far the lowest axial shrinkage on Capsule 3 compacts�

Survival of Listeria monocytogenes in Soil Requires AgrA-Mediated Regulation.

Science.gov (United States)

Vivant, Anne-Laure; Garmyn, Dominique; Gal, Laurent; Hartmann, Alain; Piveteau, Pascal

2015-08-01

In a recent paper, we demonstrated that inactivation of the Agr system affects the patterns of survival of Listeria monocytogenes (A.-L. Vivant, D. Garmyn, L. Gal, and P. Piveteau, Front Cell Infect Microbiol 4:160, http://dx.doi.org/10.3389/fcimb.2014.00160). In this study, we investigated whether the Agr-mediated response is triggered during adaptation in soil, and we compared survival patterns in a set of 10 soils. The fate of the parental strain L. monocytogenes L9 (a rifampin-resistant mutant of L. monocytogenes EGD-e) and that of a ΔagrA deletion mutant were compared in a collection of 10 soil microcosms. The ΔagrA mutant displayed significantly reduced survival in these biotic soil microcosms, and differential transcriptome analyses showed large alterations of the transcriptome when AgrA was not functional, while the variations in the transcriptomes between the wild type and the ΔagrA deletion mutant were modest under abiotic conditions. Indeed, in biotic soil environments, 578 protein-coding genes and an extensive repertoire of noncoding RNAs (ncRNAs) were differentially transcribed. The transcription of genes coding for proteins involved in cell envelope and cellular processes, including the phosphotransferase system and ABC transporters, and proteins involved in resistance to antimicrobial peptides was affected. Under sterilized soil conditions, the differences were limited to 86 genes and 29 ncRNAs. These results suggest that the response regulator AgrA of the Agr communication system plays important roles during the saprophytic life of L. monocytogenes in soil. Copyright © 2015, American Society for Microbiology. All Rights Reserved.

Multicycle Optimization of Advanced Gas-Cooled Reactor Loading Patterns Using Genetic Algorithms

International Nuclear Information System (INIS)

Ziver, A. Kemal; Carter, Jonathan N.; Pain, Christopher C.; Oliveira, Cassiano R.E. de; Goddard, Antony J. H.; Overton, Richard S.

2003-01-01

A genetic algorithm (GA)-based optimizer (GAOPT) has been developed for in-core fuel management of advanced gas-cooled reactors (AGRs) at HINKLEY B and HARTLEPOOL, which employ on-load and off-load refueling, respectively. The optimizer has been linked to the reactor analysis code PANTHER for the automated evaluation of loading patterns in a two-dimensional geometry, which is collapsed from the three-dimensional reactor model. GAOPT uses a directed stochastic (Monte Carlo) algorithm to generate initial population members, within predetermined constraints, for use in GAs, which apply the standard genetic operators: selection by tournament, crossover, and mutation. The GAOPT is able to generate and optimize loading patterns for successive reactor cycles (multicycle) within acceptable CPU times even on single-processor systems. The algorithm allows radial shuffling of fuel assemblies in a multicycle refueling optimization, which is constructed to aid long-term core management planning decisions. This paper presents the application of the GA-based optimization to two AGR stations, which apply different in-core management operational rules. Results obtained from the testing of GAOPT are discussed

Characterisation of AGR fuel cladding alloy using secondary ion mass spectrometry

International Nuclear Information System (INIS)

Allen, G.C.; Sparry, R.P.; Wild, R.K.

1987-08-01

Uranium dioxide fuel used in the Advanced Gas Cooled Reactor (AGR) is contained in a ribbed can of 20wt%Cr/25wt%Ni/Nb stabilised steel. Laboratory circumstances, spall during thermal cycling. To date it has been difficult to identify active material originating from the oxidation product of the cladding alloy in the cooling circuit. In an attempt to solve this problem we have set out to characterise fully a sample of oxide from this source and work is in progress to obtain suitable oxide samples from the surface of a 20%Cr/25%Ni/Nb stainless steel. In view of its high sensitivity and the ability to obtain chemical information from relatively small areas we have sought to use Secondary Ion Mass Spectroscopy (SIMS). (author)

AGR fuel management using PANTHER

International Nuclear Information System (INIS)

Haddock, S.A.; Parks, G.T.

1995-01-01

This paper describes recent improvements in the AGR fuel management methodology implemented within PANTHER and the use of the code both for stand-alone calculations and within an automatic optimisation procedure. (author)

Crystal Structure of AGR_C_4470p from Agrobacterium tumefaciens

Energy Technology Data Exchange (ETDEWEB)

Vorobiev,S.; Neely, H.; Seetharaman, J.; Ma, L.; Xiao, R.; Acton, T.; Montelione, G.; Tong, L.

2007-01-01

We report here the crystal structure at 2.0 {angstrom} resolution of the AGR{_}C{_}4470p protein from the Gram-negative bacterium Agrobacterium tumefaciens. The protein is a tightly associated dimer, each subunit of which bears strong structural homology with the two domains of the heme utilization protein ChuS from Escherichia coli and HemS from Yersinia enterocolitica. Remarkably, the organization of the AGR{_}C{_}4470p dimer is the same as that of the two domains in ChuS and HemS, providing structural evidence that these two proteins evolved by gene duplication. However, the binding site for heme, while conserved in HemS and ChuS, is not conserved in AGR{_}C{_}4470p, suggesting that it probably has a different function. This is supported by the presence of two homologs of AGR{_}C{_}4470p in E. coli, in addition to the ChuS protein.

A numerical study of internal brick stresses in AGR moderator bricks

Energy Technology Data Exchange (ETDEWEB)

McNally, K., E-mail: kevin.mcnally@hsl.gsi.gov.uk [Health and Safety Laboratory, Harpur Hill, Buxton, Derbyshire SK17 9JN (United Kingdom); Fahad, M. [NGRG, School of MACE, University of Manchester, Manchester M13 9PL (United Kingdom); Tan, E.; Warren, N. [Health and Safety Laboratory, Harpur Hill, Buxton, Derbyshire SK17 9JN (United Kingdom); Hall, G.N.; Marsden, B.J. [NGRG, School of MACE, University of Manchester, Manchester M13 9PL (United Kingdom)

2016-12-01

Highlights: • A methodology for studying the uncertainty in internal brick stresses was developed. • A computationally efficient methodology based upon a surrogate model was utilised. • Uncertainty in material relationships, particularly those related to secondary creep was the dominant source of uncertainty. - Abstract: Physically-based models are often used to model changes in geometry and the associated stress fields of graphite moderator bricks within an advanced gas-cooled reactor (AGR). These models require inputs that describe the loading conditions, and coded relationships describing the behaviour of material properties. Material relationships are primarily based upon data obtained from inspection campaigns at operating reactors. However, the data from trepanning campaigns do not provide information on some of the key relationships and parameters that affect the internal stresses generated within the moderator bricks. In this work we explore how uncertain material property relationships affect the internal brick stresses in early- and late-life. We describe two computer experiments designed to study early- and late-life brick stresses and report the results from global sensitivity analysis of the models. The work makes use of an emulator, a surrogate for the FE model, in order to make the sensitivity analyses computationally feasible.

A numerical study of internal brick stresses in AGR moderator bricks

International Nuclear Information System (INIS)

McNally, K.; Fahad, M.; Tan, E.; Warren, N.; Hall, G.N.; Marsden, B.J.

2016-01-01

Highlights: • A methodology for studying the uncertainty in internal brick stresses was developed. • A computationally efficient methodology based upon a surrogate model was utilised. • Uncertainty in material relationships, particularly those related to secondary creep was the dominant source of uncertainty. - Abstract: Physically-based models are often used to model changes in geometry and the associated stress fields of graphite moderator bricks within an advanced gas-cooled reactor (AGR). These models require inputs that describe the loading conditions, and coded relationships describing the behaviour of material properties. Material relationships are primarily based upon data obtained from inspection campaigns at operating reactors. However, the data from trepanning campaigns do not provide information on some of the key relationships and parameters that affect the internal stresses generated within the moderator bricks. In this work we explore how uncertain material property relationships affect the internal brick stresses in early- and late-life. We describe two computer experiments designed to study early- and late-life brick stresses and report the results from global sensitivity analysis of the models. The work makes use of an emulator, a surrogate for the FE model, in order to make the sensitivity analyses computationally feasible.

Use of oxygen dosing to prevent flow accelerated corrosion in British Energy's Advanced Gas-Cooled Reactors

International Nuclear Information System (INIS)

Quirk, G.P.; Woolsey, I.S.; Rudge, A.

2010-01-01

Flow accelerated corrosion (FAC) was recognized as major threat to the carbon steel feed and economizer tubing of the once-through boilers of the UK's Advanced Gas-cooled Reactors (AGRs) following the observation of FAC damage of the boiler inlet orifice assemblies at two plants in 1977, and subsequent review of the likelihood of further damage elsewhere within the boilers of all AGRs. In most cases, replacement of susceptible tubing was not feasible; due to the inaccessibility of the boiler components within the reactor concrete pressure vessel. Preventing further FAC damage within the boilers therefore had to rely largely on changes to the boiler feedwater chemistry. Following extensive research programs carried out in the late 1970s and early 1980s two main feedwater chemistry regimes were adopted to suppress FAC in different AGRs. The four units found to be at greatest risk of FAC damage adopted an oxygen dosed All Volatile Treatment (AVT) regime during commissioning, while four other units retained the original deoxygenated ammonia dosed AVT regime, but with an increased feedwater pH. The deoxygenated ammonia dosed chemistry regime was also adopted in four AGR units subsequently built, which used 1%Cr0.5%Mo feed and economizer tubing in their once-through boilers. The oxygen dosed AVT chemistry regime adopted in four units having helical once-through boilers has proved highly effective in preventing FAC, with no evidence of damage after around 150,000 hours of operation. However, FAC damage was eventually found in some of the other units operating with a deoxygenated feedwater chemistry regime, in spite of having adopted an elevated feedwater pH. These units have now successfully converted to an oxygen dosed AVT feedwater chemistry regime to prevent further FAC damage, with the result that all 14 AGR reactors now operate with variants of the original oxygen dosed feedwater chemistry regime developed during the 1980s. The paper outlines the development of

La Elvira, desarrollo agrícola olvidado (caso real

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Álvaro Camacho Caicedo

2007-01-01

Full Text Available En éste artículo, se hace una reflexión crítica sobre la concepción que tradicionalmente han tenido los lideres y dirigentes de las instituciones gubernamentales, privadas y académicas relacionadas con el Desarrollo Rural del Municipio, sobre la importancia de "la contribución del "subsector agrícola campesino caleño" al PIB municipal. Se resalta la relación fundamental que existe entre el nivel de productividad y competitividad que pueden llegar a alcanzar los corregimientos caleños en sus cosechas de hortalizas con los acompañamientos, fomento y apoyos de asistencia tecnológica, crédito agrícola, administración de cultivos y comercialización por parte de las instituciones mencionadas. La falta de apoyos interinstitucionales genera en la comunidad el efecto contrario. En el presente artículo se plantean propuestas, estrategias y políticas para el desarrollo agrícola del corregimiento caleño de La Elvira, basadas en la experiencia del autor como economista agrícola y de otras personas interesadas y conocedoras del tema.

Initial Gamma Spectrometry Examination of the AGR-3/4 Irradiation

Energy Technology Data Exchange (ETDEWEB)

Harp, Jason M.; Demkowicz, Paul A.; Stempien, John D.

2016-11-01

The initial results from gamma spectrometry examination of the different components from the combined third and fourth US Advanced Gas Reactor Fuel Development TRISO-coated particle fuel irradiation tests (AGR-3/4) have been analyzed. This experiment was designed to provide information about in-pile fission product migration. In each of the 12 capsules, a single stack of four compacts with designed-to-fail particles surrounded by two graphitic diffusion rings (inner and outer) and a graphite sink were irradiated in the Idaho National Laboratory’s Advanced Test Reactor. Gamma spectrometry has been used to evaluate the gamma-emitting fission product inventory of compacts from the irradiation and evaluate the burnup of these compacts based on the activity of the radioactive cesium isotopes (Cs-134 and Cs-137) in the compacts. Burnup from gamma spectrometry compares well with predicted burnup from simulations. Additionally, inner and outer rings were also examined by gamma spectrometry both to evaluate the fission product inventory and the distribution of gamma-emitting fission products within the rings using gamma emission computed tomography. The cesium inventory of the scanned rings compares acceptably well with the expected inventory from fission product transport modeling. The inventory of the graphite fission product sinks is also being evaluated by gamma spectrometry.

Corrosion inhibition studies in support of the long term storage of AGR fuel

Energy Technology Data Exchange (ETDEWEB)

Standring, P [Sellafield Limited (United Kingdom)

2012-07-01

Thorp Receipt and Storage (at Sellafield, UK) is currently being investigated as a bridging solution for the storage of AGR fuel pending the out-come of a national review into spent fuel management. AGR spent fuel is known to be susceptible to corrosion through inter-granular attack. To avoid this, the chosen storage regime for AGR fuel is sodium hydroxide dosed pond water to pH 11.4; now 22 years of operating experience. The conversion of TR and S will require a phased transition. During this transition sodium hydroxide cannot be used due to materials compatibility issues. Alternative corrosion inhibitors have been investigated as an interim measure and sodium nitrate has been selected as a suitable candidate. The efficiency of sodium nitrate to inhibit propagating inter-granular attack of active AGR materials has yet to be established. In the longer term sodium hydroxide will be deployed along with a move to a closed loop pond water management system. Given that carbon dioxide is known to be absorbed by sodium hydroxide dosed water and can affect fuel integrity, in the case of Magnox fuel, there is a need to establish its impact on AGR fuel. The objectives are: To establish the impact of carbonate on AGR fuel corrosion; To establish the efficiency of sodium nitrate to inhibit propagating inter-granular attack of irradiated AGR materials.

Saberes agrícolas tradicionales como programa académico

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J. Antonio Gómez Espinoza

2008-01-01

Full Text Available En el marco de las crisis social y ambiental del tercer milenio, se hace necesario repensar la universidad, sus paradigmas, el concepto de educación y su modelo educativo para impactar en la construcción de la nueva sociedad. Los Saberes Agrícolas Tradicionales (SAT aportan elementos conceptuales básicos para la implementación y desarrollo de una sociedad sustentable. A partir del rescate, la sistematización de los SAT y el diálogo intercultural SAT-ciencia, se propone incorporar los Saberes Agrícolas Tradicionales como programa académico en las Instituciones de Enseñanza y Aprendizaje Agrícola del nivel Superior (IEAS.

Radiation protection in the decommissioning of a post accident reactor

International Nuclear Information System (INIS)

Rankine, A.; Wilkinson, J.L.; Dalton, J.

1996-01-01

This paper describes the control and limitation of dose uptake to operators during the early stages of decommissioning of the Windscale Piles. This was achieved by careful planning, the use of inactive trials. thoughtful use of remote handling techniques and review and feedback of information. Built between 1947 and 1950, the Windscale Piles were shut down following the Windscale Incident in 1957. UKAEA Government Division are now undertaking the early stages of decommissioning of these facilities, removing material from the air and water ducts and preparing for subsequent core removal. As part of the overall strategy of UKAEA GD, this work is being carried out using contract staff including the use of a Managing Agency, W S Atkins (Northern). Decommissioning utilizes the same means of dose reduction and control as any other nuclear operation although sometimes in novel ways. In the Windscale Piles, fully remote operations have been used to remove fuel and debris from the environs of the core which was damaged during the 1957 incident. Much use has also been made of training in mock-up facilities allowing manual techniques to be used for some jobs. The implications of using various different contractors rather than an in-house team is also discussed. It is concluded that decommissioning of major facilities can be carried out within acceptable dose uptake criteria by utilising both novel and adaptations of traditional, active handling techniques. (author)

The Staphylococcus aureus Two-Component System AgrAC Displays Four Distinct Genomic Arrangements That Delineate Genomic Virulence Factor Signatures

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Kumari S. Choudhary

2018-05-01

Full Text Available Two-component systems (TCSs consist of a histidine kinase and a response regulator. Here, we evaluated the conservation of the AgrAC TCS among 149 completely sequenced Staphylococcus aureus strains. It is composed of four genes: agrBDCA. We found that: (i AgrAC system (agr was found in all but one of the 149 strains, (ii the agr positive strains were further classified into four agr types based on AgrD protein sequences, (iii the four agr types not only specified the chromosomal arrangement of the agr genes but also the sequence divergence of AgrC histidine kinase protein, which confers signal specificity, (iv the sequence divergence was reflected in distinct structural properties especially in the transmembrane region and second extracellular binding domain, and (v there was a strong correlation between the agr type and the virulence genomic profile of the organism. Taken together, these results demonstrate that bioinformatic analysis of the agr locus leads to a classification system that correlates with the presence of virulence factors and protein structural properties.

The Staphylococcus aureus Two-Component System AgrAC Displays Four Distinct Genomic Arrangements That Delineate Genomic Virulence Factor Signatures

Science.gov (United States)

Choudhary, Kumari S.; Mih, Nathan; Monk, Jonathan; Kavvas, Erol; Yurkovich, James T.; Sakoulas, George; Palsson, Bernhard O.

2018-01-01

Two-component systems (TCSs) consist of a histidine kinase and a response regulator. Here, we evaluated the conservation of the AgrAC TCS among 149 completely sequenced Staphylococcus aureus strains. It is composed of four genes: agrBDCA. We found that: (i) AgrAC system (agr) was found in all but one of the 149 strains, (ii) the agr positive strains were further classified into four agr types based on AgrD protein sequences, (iii) the four agr types not only specified the chromosomal arrangement of the agr genes but also the sequence divergence of AgrC histidine kinase protein, which confers signal specificity, (iv) the sequence divergence was reflected in distinct structural properties especially in the transmembrane region and second extracellular binding domain, and (v) there was a strong correlation between the agr type and the virulence genomic profile of the organism. Taken together, these results demonstrate that bioinformatic analysis of the agr locus leads to a classification system that correlates with the presence of virulence factors and protein structural properties. PMID:29887846

Caracterização dos acidentes com tratores agrícolas

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Schlosser José Fernando

2002-01-01

Full Text Available Em despeito à sua importância, poucas pesquisas vêm sendo executadas com o intuito de caracterizar os acidentes de trabalho com tratores agrícolas, identificando sua natureza (tipo bem como suas causas. O objetivo deste trabalho foi caracterizar os acidentes envolvendo tratores agrícolas ocorridos na região da Depressão Central do Rio Grande do Sul e, a partir disto, delinear estratégias eficientes na sua prevenção. Para o levantamento dos dados, foi aplicado um questionário aos operadores de tratores agrícolas da região da Depressão Central do Rio Grande do Sul. Os dados demonstraram que 39% dos trabalhadores rurais entrevistados já sofreram algum tipo de acidente de trabalho com tratores agrícolas. Dentre os tipos de acidentes com tratores agrícolas detectados na pesquisa, destacam-se o capotamento, que correspondeu a 51,71% do total de acidentes graves, e os escorregões, que corresponderam a 40,82% dos acidentes leves. As principais causas dos acidentes relatados foram a falta de conhecimento a respeito das medidas de segurança na operação de tratores (32,77%, a falta de atenção (32,22% para a tarefa executada e o equipamento inadequado (22,22%. Os acidentes graves tiveram causas diferentes comparativamente aos leves. Operadores sem treinamento adequado, a não observação de regras básicas de segurança e a longa jornada de trabalho são tendências observadas neste trabalho que ampliam os riscos de ocorrência de acidentes. A inclusão de dispositivos que tornem a máquina mais segura e confortável, bem como o treinamento dos operadores de tratores agrícolas são práticas de importância fundamental para a prevenção dos acidentes com tratores agrícolas.

Development of CO2 circulators

International Nuclear Information System (INIS)

Donaldson, J.

1988-01-01

The development of the basic machine types we have supplied has not been without problems. The Windscale AGR (the prototype AGR) was a small 1.2 MW vertically up circulator with an inlet temperature of 237 deg. C (459 deg. F). Oil leakage problems occurred and were cured in the works test facility and the machine went into service with no other problems. The Horizontal 5 MW machines for Hinkley/Hunterston were not so fortunate with vibration problems, interface corrosion problems (effecting the whole reactor) and material dimensional stability problems. Oil ingress problems did not show up in test work but were later reported from site. These reports were initially exagerated due to the measuring techniques which took the operators some time to resolve. In the vertical 5 MW machines for Hartlepool and Heysham 1 there are two interesting factors, firstly a spar failure and secondly shaft axial stability. Many of the problems were due to modifications at site or our inability to model all aspects of site installation from which lessons for the future can be learned. The latest stations Torness and Heysham II incorporate these lessons. The machines have been designed with so much margin that during the resolution of the reactor control rod gag problems the machines were run continuously at 20% overload (6.3 MW). From an initial accident case of 350 deg. C inlet temperature, this increased to 458 deg. C and now stands at 585 deg. C. No modifications to the impeller were required. The site experience to date is good with no operational problems reported. (author). 4 figs

Power from plutonium: fast reactor fuel

International Nuclear Information System (INIS)

Bishop, J.F.W.

1981-01-01

Points of similarity and of difference between fast reactor fuel and fuels for AGR and PWR plants are established. The flow of uranium and plutonium in fast and thermal systems is also mentioned, establishing the role of the fast reactor as a plutonium burner. A historical perspective of fast reactors is given in which the substantial experience accumulated in test and prototype is indicated and it is noted that fast reactors have now entered the commercial phase. The relevance of the data obtained in the test and prototype reactors to the behaviour of commercial fast reactor fuel is considered. The design concepts employed in fuel are reviewed, including sections on core support styles, pin support and pin detail. This is followed by a discussion of current issues under the headings of manufacture, performance and reprocessing. This section includes a consideration of gel fuel, achievable burn-up, irradiation induced distortions and material choices, fuel form, and fuel failure mechanisms. Future development possibilities are also discussed and the Paper concludes with a view on the logic of a UK fast reactor strategy. (U.K.)

Trabajadores agrícolas y subjetividad en California

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Florencio Posadas Segura

2014-01-01

Full Text Available En este trabajo se explora el problema de la subjetividad de los trabajadores agríco - las, partiendo de la hipótesis de que éstos consideran malas sus condiciones de vida y de trabajo. Mediante el trabajo de campo se demostraron sus conocimientos y opi - niones sobre su situación laboral y existencial en el Valle de San Joaquín California durante 2007 y 2008. Se descubrió que la visión del trabajador agrícola está basada en la subjetivación y reinterpretación de sus circunstancias objetivas de trabajo y de vida. Se concluyó que los trabajadores agrícolas opinan que sus condiciones son pé - simas porque sus derechos laborales, sociales y humanos no se reconocen o respetan, la crisis económica, social y política de Estados Unidos les perjudica y el Tratado de Libre Comercio entre México, Estados Unidos y Canadá ( TLCAN sólo podría beneficiarles con una reforma migratoria.

Methods for studying fuel management in advanced gas cooled reactors

International Nuclear Information System (INIS)

Buckler, A.N.; Griggs, C.F.; Tyror, J.G.

1971-07-01

The methods used for studying fuel and absorber management problems in AGRs are described. The basis of the method is the use of ARGOSY lattice data in reactor calculations performed at successive time steps. These reactor calculations may be quite crude but for advanced design calculations a detailed channel-by-channel representation of the whole core is required. The main emphasis of the paper is in describing such an advanced approach - the ODYSSEUS-6 code. This code evaluates reactor power distributions as a function of time and uses the information to select refuelling moves and determine controller positions. (author)

The design and construction of the windscale vitrification plant and vitrified product store

International Nuclear Information System (INIS)

Heafield, W.; Woodall, A.; Elsden, A.D.

1987-01-01

The paper describes the background of High Level Waste storage and vitrification development in the UK and its application to Reprocessing Operations at Sellafield. The main stages in the vitrification process and associated maintenance facilities are described together with the layout of the Windscale Vitrification Plant (WVP) and associated Vitrified Product Store (VPS). The design and construction techniques employed for example, the use of Computer Aided Design and the effect of automatic pipe bending/orbital welding and the use of precast units for cell construction, are discussed and current construction progress is highlighted. The vitrification process uses complex mechanical plant operating in high temperature and radiation fields. An extensive engineering and process development programme has been carried out. A full scale inactive facility (FSIF) has been constructed and the objectives and results from the operation of FSIF are presented. In addition to engineering and process development, a comprehensive programme of glass technology development has been carried out to establish maximum waste incorporation levels, reaction kinetic and product properties of the candidate glass formulations

The design and development of AGR fuelling machines

International Nuclear Information System (INIS)

Calnan, J.P.; Hardon, L.

1986-01-01

The main functional requirements and essential generic design aspects of the UK AGR fuelling machines are listed and described as a precursor to reviewing some detail features of the individual station designs. The paper highlights the variability of engineering solutions adopted to meet the common challenge of on-load refuelling the first generation AGR stations. Design development from first to second generation stations is illustrated by detailed reference to the Hinkley B/Hunterston B and Heysham II/Torness fuelling machine designs. The paper concludes with a brief speculative view on the possible direction of future design development. (author)

Monitoring of irradiation effects on the pressure vessel steels of Calder, Chapelcross and Windscale Advanced Gas Cooled Reactor (WAGR) nuclear reactors

International Nuclear Information System (INIS)

Turner, F.

1980-01-01

Tensile, Charpy and bend specimens of plate, forging and weld metal are exposed in the lower and upper zones of the reactors to neutron fluxes covering the range experienced by the vessels. The test conditions are described, the results presented and discussed. (author)

Competencias Profesionales del Ingeniero Agrónomo de la Universidad de Guanajuato Competencias Profesionales del Ingeniero Agrónomo de la Universidad de Guanajuato

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Gabriel Córdova Duarte

2012-02-01

Full Text Available Buscando determinar las competencias profesionales del Ingeniero Agrónomo, se realizó una revisión bibliográfi ca de la problemática agrícola del estado de Guanajuato, sobre las características y tipos de competencias, requeridas en éste contexto. Las mismas se identificaron y clasificaron de la siguiente manera: técnicas, establecer, implementar y evaluar las diversas técnicas de producción de cultivos; realizar un uso eficiente del agua; conservar, recuperar y optimizar el suelo; seleccionar y manejar maquinaria y equipo agropecuario; diagnosticar, controlar y prevenir las plagas, malezas y enfermedades de los cultivos; las metodológicas: analizar, implementar y evaluar diversas estrategias de venta y comercialización de productos y subproductos agrícolas; administrar empresas y proyectos agrícolas; y, establecer, implementar y evaluar alternativas energéticas agrícolas; la social participativa: diseñar, implementar y evaluar diversas estrategias para el desarrollo rural. Por tanto, la formación del agrónomo debe brindar estas competencias, a fin de contribuir al mejoramiento de la problemática estatal. In order to determine the professional competencies needed by Agricultural Engineers, a bibliographic review of agricultural problems in the state of Guanajuato was performed, focused on the types and characteristics of competencies needed, which were identified and classified as follows: Techniques for the establishment, implementation, and evaluation of various methods of crop production; the efficient use of water; the conservation, recuperation, and optimization of soil; the selection and use of machinery and farming equipment; and the diagnosing, control, and prevention of weeds, vermin, and crop diseases; Methodologies for the analysis, implementation, and evaluation of various sales strategies and the commercialization of agricultural products and sub-products; the administration of companies and agricultural

Cross-Talk between Staphylococcus aureus and Other Staphylococcal Species via the agr Quorum Sensing System

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Jaime Canovas

2016-11-01

Full Text Available Staphylococci are associated with both humans and animals. While most are non-pathogenic colonizers, Staphylococcus aureus is an opportunistic pathogen capable of causing severe infections. S. aureus virulence is controlled by the agr quorum sensing system responding to secreted auto-inducing peptides (AIPs sensed by AgrC, a two component histidine kinase. agr loci are found also in other staphylococcal species and for Staphylococcus epidermidis, the encoded AIP represses expression of agr regulated virulence genes in S. aureus. In this study we aimed to better understand the interaction between staphylococci and S. aureus, and show that this interaction may eventually lead to the identification of new anti-virulence candidates to target S. aureus infections. Here we show that culture supernatants of 37 out of 52 staphylococcal isolates representing 17 different species inhibit S. aureus agr. The dog pathogen, Staphylococcus schleiferi, expressed the most potent inhibitory activity and was active against all four agr classes found in S. aureus. By employing a S. aureus strain encoding a constitutively active AIP receptor we show that the activity is mediated via agr. Subsequent cloning and heterologous expression of the S. schleiferi AIP in S. aureus demonstrated that this molecule was likely responsible for the inhibitory activity, and further proof was provided when pure synthetic S. schleiferi AIP was able to completely abolish agr induction of an S. aureus reporter strain. To assess impact on S. aureus virulence, we co-inoculated S. aureus and S. schleiferi in vivo in the Galleria mellonella wax moth larva, and found that expression of key S. aureus virulence factors was abrogated. Our data show that the S. aureus agr locus is highly responsive to other staphylococcal species suggesting that agr is an inter-species communication system. Based on these results we speculate that interactions between S. aureus and other colonizing staphylococci

La ingeniería agrícola en el mundo

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José Eugenio Hernández H.

1989-07-01

Full Text Available Con el objeto de dar a conocer el grado de difusión que la ingeniería agrícola tiene en el mundo, en el presente artículo se indican la mayoría de los países y las universidades que en los distintos continentes ofrecen programas de pregrado y postgrado en ingeniería agrícola y áreas afines. Se trata de una recopilación de la información disponible en diferentes fuentes; pretendemos que sirva de punto de apoyo en la obtención de mayores datos para aquellas personas interesadas en iniciar la carrera a nivel de pregrado o bien en cursar estudios de postgrado en una de las áreas específicas de acción profesional de la ingeniería agrícola.

Steam generator materials constraints in UK design gas-cooled reactors

International Nuclear Information System (INIS)

James, D.W.

1988-01-01

A widely reported problem with Magnox-type reactors was the oxidation of carbon steel components in gas circuits and steam generators. The effects of temperature, pressure, gas composition and steel composition on oxidation kinetics have been determined, thus allowing the probabilities of failure of critical components to be predicted for a given set of operating conditions. This risk analysis, coupled with regular inspection of reactor and boiler internals, has allowed continued operation of all U.K. Magnox plant. The Advanced Gas Cooled Reactor (AGR) is a direct development of the Magnox design. The first four AGRs commenced operation in 1976, at Hinkley Point 'B' and at Hunterston 'B'. All known materials problems with the steam generators have been diagnosed and solved by the development of appropriate operational strategies, together with minor plant modifications. Materials constraints no longer impose any restrictions to full load performance from the steam generators throughout the predicted life of the plant. Problems discussed in detail are: 1. oxidation of the 9 Cr - 1 Mo superheater. 2. Stress corrosion of the austenitic superheater. 3. Creep of the transition joints between the 9 Cr - 1 Mo and austenitic sections. With the 9 Cr - 1 Mo oxidation maximum temperature restriction virtually removed and creep constraints properly quantified, boiler operation in now favourably placed. Stress corrosion research has allowed the risk of tube failure to be related to time, temperature, stress and chemistry. As a result, the rigorous 'no wetting' policy has been relaxed for the normally high quality AGR feedwater, and the superheat margin has been reduced to 23 deg. C. This has increased the size of the operating window and reduced the number of expensive, and potentially harmful, plant trips. (author)

A abordagem ambiental na geografia agrária brasileira: uma análise dos periódicos Revista Agrária, Revista Campo-Território e Revista NERA

OpenAIRE

Artur Leonardo Andrade

2015-01-01

O presente estudo procurou analisar a abordagem ambiental na geografia agrária brasileira a partir dos periódicos Revista Agrária, Revista Campo-Território e Revista NERA. Para isso, foram selecionados e analisados 78 artigos que debatem, de forma direta, a questão ambiental. Como os periódicos foram criados a partir da década de 1990, a escolha metodológica possibilitou uma análise do período atual da geografia agrária, o pós-1990, marcado pela pluralidade teórico-metodológica. Esta pesquisa...

Mechanical components: fabrication of major reactor structures

International Nuclear Information System (INIS)

Nicholson, S.

1985-01-01

The paper examines the validity of criticisms of quality assurance of mechanical plant and welded products within major reactor structures, taking into account experience gained on the AGR's. Various constructive recommendations are made aimed at furthering the objectives of quality assurance in the nuclear industry and making it more cost-effective. Current levels of quality related costs in the fabrication industry are provided as a basis for discussion. (U.K.)

Política Agrícola Canadiense. Algunas lecciones para Argentina

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Rinaldo Antonio Colomé

2010-09-01

Full Text Available El objetivo general de este trabajo es analizar el diseño de la política agrícola canadiense, comparándola con las de los otros países altamente desarrollados y con la de Argentina.  Los objetivos específicos son: aAnalizar la política agrícola de Canadá referida a la producción y al comercio de granos y su efecto en los mercados internacionales; bAnalizar la política agrícola y comercial de Canadá referida al sector de oferta dirigida o regulada y sus efectos en el mercado doméstico y en los internacionales; c Realizar una comparación con Argentina. 

The Next Generation Nuclear Plant/Advanced Gas Reactor Fuel Irradiation Experiments in the Advanced Test Reactor

International Nuclear Information System (INIS)

Grover, S. Blaine

2009-01-01

The United States Department of Energy's Next Generation Nuclear Plant (NGNP) Program will be irradiating eight separate low enriched uranium (LEU) tri-isotopic (TRISO) particle fuel (in compact form) experiments in the Advanced Test Reactor (ATR) located at the Idaho National Laboratory (INL). The ATR has a long history of irradiation testing in support of reactor development and the INL has been designated as the new United States Department of Energy's lead laboratory for nuclear energy development. The ATR is one of the world's premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. These irradiations and fuel development are being accomplished to support development of the next generation reactors in the United States, and will be irradiated over the next ten years to demonstrate and qualify new particle fuel for use in high temperature gas reactors. The goals of the irradiation experiments are to provide irradiation performance data to support fuel process development, to qualify fuel for normal operating conditions, to support development and validation of fuel performance and fission product transport models and codes, and to provide irradiated fuel and materials for post irradiation examination (PIE) and safety testing. The experiments, which will each consist of at least six separate capsules, will be irradiated in an inert sweep gas atmosphere with individual on-line temperature monitoring and control of each capsule. The sweep gas will also have on-line fission product monitoring on its effluent to track performance of the fuel in each individual capsule during irradiation. The first experiment (designated AGR-1) started irradiation in December 2006, and the second experiment (AGR-2) is currently in the design phase. The design of test trains, as well as the support systems and fission product monitoring system that will monitor and control the experiment during irradiation will be discussed. In

The Agr Quorum Sensing System Represses Persister Formation through Regulation of Phenol Soluble Modulins in Staphylococcus aureus

Directory of Open Access Journals (Sweden)

Tao Xu

2017-11-01

Full Text Available The opportunistic pathogen Staphylococcus aureus has become an increasing threat to public health. While the Agr quorum sensing (QS system is a master regulator of S. aureus virulence, its dysfunction has been frequently reported to promote bacteremia and mortality in clinical infections. Here we show that the Agr system is involved in persister formation in S. aureus. Mutation of either agrCA or agrD but not RNAIII resulted in increased persister formation of stationary phase cultures. RNA-seq analysis showed that in stationary phase AgrCA/AgrD and RNAIII mutants showed consistent up-regulation of virulence associated genes (lip and splE, etc. and down-regulation of metabolism genes (bioA and nanK, etc.. Meanwhile, though knockout of agrCA or agrD strongly repressed expression of phenol soluble modulin encoding genes psmα1-4, psmβ1-2 and phenol soluble modulins (PSM transporter encoding genes in the pmt operon, mutation of RNAIII enhanced expression of the genes. We further found that knockout of psmα1-4 or psmβ1-2 augmented persister formation and that co-overexpression of PSMαs and PSMβs reversed the effects of AgrCA mutation on persister formation. We also detected the effects on persister formation by mutations of metabolism genes (arcA, hutU, narG, nanK, etc. that are potentially regulated by Agr system. It was found that deletion of the ManNAc kinase encoding gene nanK decreased persister formation. Taken together, these results shed new light on the PSM dependent regulatory role of Agr system in persister formation and may have implications for clinical treatment of MRSA persistent infections.

Heysham II/Torness AGR core integrity

International Nuclear Information System (INIS)

Birch, A.L.; Hampson, J.D.

1985-01-01

The design and construction process for the Heysham II/Torness AGR core structures is presented. The design intent utilizing all past experience in designing and building AGR core structures is described. The major aspects of the design criteria and the design conditions are outlined to demonstrate how the integrity of the Heysham II/Torness core is assured. Since no recognized codes of practice for graphite core design exist, the National Nuclear Corporation (NNC) have conceived design criteria utilizing reserve factors based on their design experience. Target reserve factors are defined for particular loading conditions including the ultimate 'safe-shutdown earthquake'. The substantial programme of computer analysis and RandD work to substantiate the design, including seismic qualification, is described. In keeping with their responsibility for the detailed core structure design and the fuel path geometry (guide tube system), NNC attach great importance to design/manufacture/construction liaison, which is demonstrated in the quality assurance section. (author)

The development of criteria for the design of insulation for nuclear reactors

International Nuclear Information System (INIS)

Furber, B.N.; Hopkins, I.H.G.; Stuart, R.A.

1976-01-01

In 1960 when the early design studies for the Oldbury Power Station were being carried out the use of insulation in a reactor environment was quite novel. No manufacturer had previous experience of this particular application of insulation. The paper describes the work carried out to establish the design criteria for Magnox and subsequent Advanced Gas Cooled Reactors (AGR) and indicates some of the new problems of the High Temperature Reactor (HTR). Unless otherwise stated the work was carried out by The Nuclear Power Group Ltd. (TNPG) and the conclusions express the present thinking of that Company. (author)

CD147 and AGR2 expression promote cellular proliferation and metastasis of head and neck squamous cell carcinoma

International Nuclear Information System (INIS)

Sweeny, Larissa; Liu, Zhiyong; Bush, Benjamin D.; Hartman, Yolanda; Zhou, Tong; Rosenthal, Eben L.

2012-01-01

The signaling pathways facilitating metastasis of head and neck squamous cell carcinoma (HNSCC) cells are not fully understood. CD147 is a transmembrane glycoprotein known to induce cell migration and invasion. AGR2 is a secreted peptide also known to promote cell metastasis. Here we describe their importance in the migration and invasion of HNSCC cells (FADU and OSC-19) in vitro and in vivo. In vitro, knockdown of CD147 or AGR2 decreased cellular proliferation, migration and invasion. In vivo, knockdown of CD147 or AGR2 expression decreased primary tumor growth as well as regional and distant metastasis. -- Highlights: ► We investigated AGR2 in head and neck squamous cell carcinoma for the first time. ► We explored the relationship between AGR2 and CD147 for the first time. ► AGR2 and CD147 appear to co-localize in head and squamous cell carcinoma samples. ► Knockdown of both AGR2 and CD147 reduced migration and invasion in vitro. ► Knockdown of both AGR2 and CD147 decreased metastasis in vivo.

KEY RESULTS FROM IRRADIATION AND POST-IRRADIATION EXAMINATION OF AGR-1 UCO TRISO FUEL

Energy Technology Data Exchange (ETDEWEB)

Demkowicz, Paul A.; Hunn, John D.; Petti, David A.; Morris, Robert N.

2016-11-01

The AGR-1 irradiation experiment was performed as the first test of tristructural isotropic (TRISO) fuel in the US Advanced Gas Reactor Fuel Development and Qualification Program. The experiment consisted of 72 right cylinder fuel compacts containing approximately 3×105 coated fuel particles with uranium oxide/uranium carbide (UCO) fuel kernels. The fuel was irradiated in the Advanced Test Reactor for a total of 620 effective full power days. Fuel burnup ranged from 11.3 to 19.6% fissions per initial metal atom and time average, volume average irradiation temperatures of the individual compacts ranged from 955 to 1136°C. This paper focuses on key results from the irradiation and post-irradiation examination, which revealed a robust fuel with excellent performance characteristics under the conditions tested and have significantly improved the understanding of UCO coated particle fuel irradiation behavior within the US program. The fuel exhibited a very low incidence of TRISO coating failure during irradiation and post-irradiation safety testing at temperatures up to 1800°C. Advanced PIE methods have allowed particles with SiC coating failure to be isolated and meticulously examined, which has elucidated the specific causes of SiC failure in these specimens. The level of fission product release from the fuel during irradiation and post-irradiation safety testing has been studied in detail. Results indicated very low release of krypton and cesium through intact SiC and modest release of europium and strontium, while also confirming the potential for significant silver release through the coatings depending on irradiation conditions. Focused study of fission products within the coating layers of irradiated particles down to nanometer length scales has provided new insights into fission product transport through the coating layers and the role various fission products may have on coating integrity. The broader implications of these results and the application of

Irradiation performance of AGR-1 high temperature reactor fuel

Energy Technology Data Exchange (ETDEWEB)

Paul A. Demkowicz; John D. Hunn; Robert N. Morris; Charles A. Baldwin; Philip L. Winston; Jason M. Harp; Scott A. Ploger; Tyler Gerczak; Isabella J. van Rooyen; Fred C. Montgomery; Chinthaka M. Silva

2014-10-01

The AGR-1 experiment contained 72 low-enriched uranium oxide/uranium carbide TRISO-coated particle fuel compacts in six capsules irradiated to burnups of 11.2 to 19.5% FIMA, with zero TRISO coating failures detected during the irradiation. The irradiation performance of the fuel–including the extent of fission product release and the evolution of kernel and coating microstructures–was evaluated based on detailed examination of the irradiation capsules, the fuel compacts, and individual particles. Fractional release of 110mAg from the fuel compacts was often significant, with capsule-average values ranging from 0.01 to 0.38. Analysis of silver release from individual compacts indicated that it was primarily dependent on fuel temperature history. Europium and strontium were released in small amounts through intact coatings, but were found to be significantly retained in the outer pyrocrabon and compact matrix. The capsule-average fractional release from the compacts was 1×10 4 to 5×10 4 for 154Eu and 8×10 7 to 3×10 5 for 90Sr. The average 134Cs release from compacts was <3×10 6 when all particles maintained intact SiC. An estimated four particles out of 2.98×105 experienced partial cesium release due to SiC failure during the irradiation, driving 134Cs release in two capsules to approximately 10 5. Identification and characterization of these particles has provided unprecedented insight into the nature and causes of SiC coating failure in high-quality TRISO fuel. In general, changes in coating morphology were found to be dominated by the behavior of the buffer and inner pyrolytic carbon (IPyC), and infrequently observed SiC layer damage was usually related to cracks in the IPyC. Palladium attack of the SiC layer was relatively minor, except for the particles that released cesium during irradiation, where SiC corrosion was found adjacent to IPyC cracks. Palladium, silver, and uranium were found in the SiC layer of irradiated particles, and characterization

The Agr communication system provides a benefit to the populations of Listeria monocytogenes in soil.

Science.gov (United States)

Vivant, Anne-Laure; Garmyn, Dominique; Gal, Laurent; Piveteau, Pascal

2014-01-01

In this study, we investigated whether the Agr communication system of the pathogenic bacterium Listeria monocytogenes was involved in adaptation and competitiveness in soil. Alteration of the ability to communicate, either by deletion of the gene coding the response regulator AgrA (response-negative mutant) or the signal pro-peptide AgrD (signal-negative mutant), did not affect population dynamics in soil that had been sterilized but survival was altered in biotic soil suggesting that the Agr system of L. monocytogenes was involved to face the complex soil biotic environment. This was confirmed by a set of co-incubation experiments. The fitness of the response-negative mutant was lower either in the presence or absence of the parental strain but the fitness of the signal-negative mutant depended on the strain with which it was co-incubated. The survival of the signal-negative mutant was higher when co-cultured with the parental strain than when co-cultured with the response-negative mutant. These results showed that the ability to respond to Agr communication provided a benefit to listerial cells to compete. These results might also indicate that in soil, the Agr system controls private goods rather than public goods.

Decommissioning the WAGR

Energy Technology Data Exchange (ETDEWEB)

Lawton, H. (UKAEA Windscale Nuclear Power Development Labs.)

1982-11-01

The planned decommissioning of the Windscale Advanced Gas-cooled Reactor, which will take about ten years, is discussed with especial reference to the radioactive decay of the reactor components, the problems of disposal of the resulting radioactive waste, and the planning of the necessary engineering works.

Geografia agrícola brasileira: gênese e diversidad

OpenAIRE

Suzuki, Julio César

2009-01-01

A geografia agrícola é muito recente. A sua definição como um fragmento de conhecimento não possui mais de meio século. No entanto, o conhecimento sobre o campo é quase tão antigo quanto a história do homem, pelo menos aquela referente ao homem, cuja prática da agricultura alterou as possibilidades de desenvolvimento social. Desta forma, entendemos a geografia agrária como um momento particular de estruturação de conhecimentos sobre o campo e a agricultura, com base na sistematização do conhe...

Anterior Gradient 2 (AGR2) Induced Epidermal Growth Factor Receptor (EGFR) Signaling Is Essential for Murine Pancreatitis-Associated Tissue Regeneration

Science.gov (United States)

Wodziak, Dariusz; Dong, Aiwen; Basin, Michael F.; Lowe, Anson W.

2016-01-01

A recently published study identified Anterior Gradient 2 (AGR2) as a regulator of EGFR signaling by promoting receptor presentation from the endoplasmic reticulum to the cell surface. AGR2 also promotes tissue regeneration in amphibians and fish. Whether AGR2-induced EGFR signaling is essential for tissue regeneration in higher vertebrates was evaluated using a well-characterized murine model for pancreatitis. The impact of AGR2 expression and EGFR signaling on tissue regeneration was evaluated using the caerulein-induced pancreatitis mouse model. EGFR signaling and cell proliferation were examined in the context of the AGR2-/- null mouse or with the EGFR-specific tyrosine kinase inhibitor, AG1478. In addition, the Hippo signaling coactivator YAP1 was evaluated in the context of AGR2 expression during pancreatitis. Pancreatitis-induced AGR2 expression enabled EGFR translocation to the plasma membrane, the initiation of cell signaling, and cell proliferation. EGFR signaling and tissue regeneration were partially inhibited by the tyrosine kinase inhibitor AG1478, but absent in the AGR2-/- null mouse. AG1478-treated and AGR2-/- null mice with pancreatitis died whereas all wild-type controls recovered. YAP1 activation was also dependent on pancreatitis-induced AGR2 expression. AGR2-induced EGFR signaling was essential for tissue regeneration and recovery from pancreatitis. The results establish tissue regeneration as a major function of AGR2-induced EGFR signaling in adult higher vertebrates. Enhanced AGR2 expression and EGFR signaling are also universally present in human pancreatic cancer, which support a linkage between tissue injury, regeneration, and cancer pathogenesis. PMID:27764193

Management of UKAEA graphite liabilities

International Nuclear Information System (INIS)

Wise, M.

2001-01-01

The UK Atomic Energy Authority (UKAEA) is responsible for managing its liabilities for redundant research reactors and other active facilities concerned with the development of the UK nuclear technology programme since 1947. These liabilities include irradiated graphite from a variety of different sources including low irradiation temperature reactor graphite (the Windscale Piles 1 and 2, British Energy Pile O and Graphite Low Energy Experimental Pile at Harwell and the Material Testing Reactors at Harwell and Dounreay), advanced gas-cooled reactor graphite (from the Windscale Advanced Gas-cooled Reactor) and graphite from fast reactor systems (neutron shield graphite from the Dounreay Prototype Fast Reactor and Dounreay Fast Reactor). The decommissioning and dismantling of these facilities will give rise to over 6,000 tonnes of graphite requiring disposal. The first graphite will be retrieved from the dismantling of Windscale Pile 1 and the Windscale Advanced Gas-cooled Reactor during the next five years. UKAEA has undertaken extensive studies to consider the best practicable options for disposing of these graphite liabilities in a manner that is safe whilst minimising the associated costs and technical risks. These options include (but are not limited to), disposal as Low Level Waste, incineration, or encapsulation and disposal as Intermediate Level Waste. There are a number of technical issues associated with each of these proposed disposal options; these include Wigner energy, radionuclide inventory determination, encapsulation of graphite dust, galvanic coupling interactions enhancing the corrosion of mild steel and public acceptability. UKAEA is currently developing packaging concepts and designing packaging plants for processing these graphite wastes in consultation with other holders of graphite wastes throughout Europe. 'Letters of Comfort' have been sought from both the Low Level Waste and the Intermediate Level Waste disposal organisations to support the

CD147 and AGR2 expression promote cellular proliferation and metastasis of head and neck squamous cell carcinoma

Energy Technology Data Exchange (ETDEWEB)

Sweeny, Larissa, E-mail: larissasweeny@gmail.com [Department of Surgery, University of Alabama, Division of Otolaryngology-Head and Neck Surgery, 1670 University Boulevard, Volker Hall G082, Birmingham, Alabama (United States); Liu, Zhiyong; Bush, Benjamin D.; Hartman, Yolanda [Department of Surgery, University of Alabama, Division of Otolaryngology-Head and Neck Surgery, 1670 University Boulevard, Volker Hall G082, Birmingham, Alabama (United States); Zhou, Tong [Department of Medicine, Division of Immunology and Rheumatology, 1825 University Boulevard, Shelby Biomedical Research Building 302, Birmingham, Alabama (United States); Rosenthal, Eben L., E-mail: oto@uab.edu [Department of Surgery, University of Alabama, Division of Otolaryngology-Head and Neck Surgery, 1670 University Boulevard, Volker Hall G082, Birmingham, Alabama (United States)

2012-08-15

The signaling pathways facilitating metastasis of head and neck squamous cell carcinoma (HNSCC) cells are not fully understood. CD147 is a transmembrane glycoprotein known to induce cell migration and invasion. AGR2 is a secreted peptide also known to promote cell metastasis. Here we describe their importance in the migration and invasion of HNSCC cells (FADU and OSC-19) in vitro and in vivo. In vitro, knockdown of CD147 or AGR2 decreased cellular proliferation, migration and invasion. In vivo, knockdown of CD147 or AGR2 expression decreased primary tumor growth as well as regional and distant metastasis. -- Highlights: Black-Right-Pointing-Pointer We investigated AGR2 in head and neck squamous cell carcinoma for the first time. Black-Right-Pointing-Pointer We explored the relationship between AGR2 and CD147 for the first time. Black-Right-Pointing-Pointer AGR2 and CD147 appear to co-localize in head and squamous cell carcinoma samples. Black-Right-Pointing-Pointer Knockdown of both AGR2 and CD147 reduced migration and invasion in vitro. Black-Right-Pointing-Pointer Knockdown of both AGR2 and CD147 decreased metastasis in vivo.

The 2009 Lindau Nobel Laureate Meeting: Peter Agre, Chemistry 2003.

Science.gov (United States)

Agre, Peter

2009-12-09

Peter Agre, born in 1949 in Northfield Minnesota, shared the 2003 Nobel Prize in Chemistry with Roderick MacKinnon for his discovery of aquaporins, the channel proteins that allow water to cross the cell membrane. Agre's interest medicine was inspired by the humanitarian efforts of the Medical Missionary program run by the Norwegians of his home community in Minnesota. Hoping to provide new treatments for diseases affecting the poor, he joined a cholera laboratory during medical school at Johns Hopkins. He found that he enjoyed biomedical research, and continued his laboratory studies for an additional year after medical school. Agre completed his clinical training at Case Western Hospitals of Cleveland and the University of North Carolina, and returned to Johns Hopkins in 1981. There, his serendipitous discovery of aquaporins was made while pursuing the identity of the Rhesus (Rh) antigen. For a century, physiologists and biophysicists had been trying to understand the mechanism by which fluid passed across the cell's plasma membrane. Biophysical evidence indicated a limit to passive diffusion of water, suggesting the existence of another mechanism for water transport across the membrane. The putative "water channel," however, could not be identified. In 1988, while attempting to purify the 30 kDa Rh protein, Agre and colleagues began investigating a 28 kDa contaminant that they believed to be a proteolytic fragment of the Rh protein. Subsequent studies over the next 3-4 years revealed that the contaminant was a membrane-spanning oligomeric protein, unrelated to the Rh antigen, and that it was highly abundant in renal tubules and red blood cells. Still, they could not assign a function to it. The breakthrough came following a visit with his friend and former mentor John Parker. After Agre described the properties of the mysterious 28 kDa protein, Parker suggested that it might be the long-sought-after water channel. Agre and colleagues tested this idea by

Carbon deposition on 20/25/Nb steel using an electrically heated AGR fuel pin

International Nuclear Information System (INIS)

Blanchard, A.; Campion, P.

1980-01-01

The radiolysis of carbon dioxide in gas-cooled reactors leads to the production of active species capable of reacting with the graphite moderator to form carbon monoxide with a resultant gradual loss of moderator. In the early days of gas-cooled reactor design, the intention was to allow the carbon monoxide concentration to increase and use this reaction product to inhibit the initial radiolysis of the carbon dioxide. Exploratory irradiation experiments using 4 to 7% carbon monoxide revealed that low density deposits ranging in colour from light grey through brown to black were found in the temperature range 470 to 600 K. In view of the fact that this type of deposition could adversely affect heat transfer processes in both fuel channels and heat exchangers, together with the fact that carbon monoxide was not sufficiently powerful as a graphite oxidation inhibitor, methane was selected as the primary inhibitor for the AGR series of power stations. This paper describes some carbon deposition experiments using an electrically heated 'dummy fuel element' linked to a recirculating carbon dioxide irradiation loop in which carbon monoxide concentration, methane concentration, fuel pin temperature and the chemical nature of the fuel pin surface were varied. (author)

Daily Thermal Predictions of the AGR-1 Experiment with Gas Gaps Varying with Time

Energy Technology Data Exchange (ETDEWEB)

Grant Hawkes; James Sterbentz; John Maki; Binh Pham

2012-06-01

A new daily as-run thermal analysis was performed at the Idaho National Laboratory on the Advanced Gas Reactor (AGR) test experiment number one at the Advanced Test Reactor (ATR). This thermal analysis incorporates gas gaps changing with time during the irradiation experiment. The purpose of this analysis was to calculate the daily average temperatures of each compact to compare with experimental results. Post irradiation examination (PIE) measurements of the graphite holder and fuel compacts showed the gas gaps varying from the beginning of life. The control temperature gas gap and the fuel compact – graphite holder gas gaps were linearly changed from the original fabrication dimensions, to the end of irradiation measurements. A steady-state thermal analysis was performed for each daily calculation. These new thermal predictions more closely match the experimental data taken during the experiment than previous analyses. Results are presented comparing normalized compact average temperatures to normalized log(R/B) Kr-85m. The R/B term is the measured release rate divided by the predicted birth rate for the isotope Kr-85m. Correlations between these two normalized values are presented.

Acceptance Test Data for Candidate AGR-5/6/7 TRISO Particle Batches BWXT Coater Batches 93165 93172 Defective IPyC Fraction and Pyrocarbon Anisotropy

Energy Technology Data Exchange (ETDEWEB)

Helmreich, Grant W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Hunn, John D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Skitt, Darren J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dyer, John A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Schumacher, Austin T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-03-01

Coated particle fuel batches J52O-16-93165, 93166, 93168, 93169, 93170, and 93172 were produced by Babcock and Wilcox Technologies (BWXT) for possible selection as fuel for the Advanced Gas Reactor Fuel Development and Qualification (AGR) Program’s AGR-5/6/7 irradiation test in the Idaho National Laboratory (INL) Advanced Test Reactor (ATR). Some of these batches may alternately be used as demonstration coated particle fuel for other experiments. Each batch was coated in a 150-mm-diameter production-scale fluidized-bed chemical vapor deposition (CVD) furnace. Tristructural isotropic (TRISO) coatings were deposited on 425-μm-nominal-diameter spherical kernels from BWXT lot J52R-16-69317 containing a mixture of 15.5%-enriched uranium carbide and uranium oxide (UCO). The TRISO coatings consisted of four consecutive CVD layers: a ~50% dense carbon buffer layer with 100-μm-nominal thickness, a dense inner pyrolytic carbon (IPyC) layer with 40-μm-nominal thickness, a silicon carbide (SiC) layer with 35-μm-nominal thickness, and a dense outer pyrolytic carbon (OPyC) layer with 40-μmnominal thickness. The TRISO-coated particle batches were sieved to upgrade the particles by removing over-sized and under-sized material, and the upgraded batches were designated by appending the letter A to the end of the batch number (e.g., 93165A).

La normalización y certificación de tractores agrícolas en México

OpenAIRE

Alma Velia Ayala Garay; Rocío Cervantes Osornio; Marco Antonio Audelo Benítez; Noé Velázquez López; José Manuel Vargas Sállago

2013-01-01

El tractor agrícola es la principal fuente de potencia dentro de una unidad de producción. Por lo tanto para los usuarios de maquinaria agrícola, resulta una prioridad contar con mecanismos que permitan dar seguridad al usuario final o productor agrícola en el funcionamiento y calidad de los tractores, para esto el objetivo del presente es dar a conocer la evolución de la normalización y certificación de la maquinaria agrícola en México, sus impactos y tendencias, por medio de una descripción...

Decommissioning the WAGR

International Nuclear Information System (INIS)

Lawton, H.

1982-01-01

The planned decommissioning of the Windscale Advanced Gas-cooled Reactor, which will take about ten years, is discussed with especial reference to the radioactive decay of the reactor components, the problems of disposal of the resulting radioactive waste, and the planning of the necessary engineering works. (U.K.)

Axisymmetric whole pin life modelling of advanced gas-cooled reactor nuclear fuel

International Nuclear Information System (INIS)

Mella, R.; Wenman, M.R.

2013-01-01

Thermo-mechanical contributions to pellet–clad interaction (PCI) in advanced gas-cooled reactors (AGRs) are modelled in the ABAQUS finite element (FE) code. User supplied sub-routines permit the modelling of the non-linear behaviour of AGR fuel through life. Through utilisation of ABAQUS’s well-developed pre- and post-processing ability, the behaviour of the axially constrained steel clad fuel was modelled. The 2D axisymmetric model includes thermo-mechanical behaviour of the fuel with time and condition dependent material properties. Pellet cladding gap dynamics and thermal behaviour are also modelled. The model treats heat up as a fully coupled temperature-displacement study. Dwell time and direct power cycling was applied to model the impact of online refuelling, a key feature of the AGR. The model includes the visco-plastic behaviour of the fuel under the stress and irradiation conditions within an AGR core and a non-linear heat transfer model. A multiscale fission gas release model is applied to compute pin pressure; this model is coupled to the PCI gap model through an explicit fission gas inventory code. Whole pin, whole life, models are able to show the impact of the fuel on all segments of cladding including weld end caps and cladding pellet locking mechanisms (unique to AGR fuel). The development of this model in a commercial FE package shows that the development of a potentially verified and future-proof fuel performance code can be created and used

La maquinaria agrícola en el siglo XX

OpenAIRE

Ruiz-Altisent, Margarita; Gil Sierra, Jacinto

2000-01-01

La evolución de la maquinaria agrícola en el siglo XX ha sido tan espectacular que, de los tres grandes avances habidos a lo largo de la historia de la maquinaria agrícola, dos de ellos podemos considerar que marcan el comienzo y el fin del siglo XX. El primer avance fundamental se dio el día en que el hombre que removía la tierra golpeándola con una herramienta tipo azada decidió avanzar con ella introducida en el suelo venciendo la fuerza de tiro. Nació así el arado en un tiempo indetermina...

Dimethylamine as a Replacement for Ammonia Dosing in the Secondary Circuit of an Advanced Gas-Cooled Reactor (AGR) Power Station

International Nuclear Information System (INIS)

Armstrong, C.; Mitchell, M.; Bull, A.; Quirk, G.P.; Rudge, A.

2012-09-01

Increasing flow resistance observed over recent years within the helical once-through boilers in the four Advanced Gas-Cooled Reactors (AGRs) at Hartlepool and Heysham 1 Power stations have reduced boiler performance, resulting in reductions in feedwater flow, steam temperatures, power output and the need to carry out periodic chemical cleaning. The root cause is believed to be the development of magnetite deposits with high flow impedance in the 9%Cr evaporator section of the boiler tubing. To prevent continued increases in boiler flow resistance, dimethylamine is being trialled, in one of the four affected units, as a replacement to the conventional ammonia dosing. Dimethylamine increases the pH at temperature around the secondary circuit and, based on full scale boiler rig simulations, is expected to reduce iron transport and prevent flow resistance increases within the evaporator section of the boiler. The dimethylamine plant trial commenced in January 2011 and is ongoing. The feedwater concentration of dimethylamine has been increased progressively towards a final target value of 900 μg kg -1 and its effect on iron transport and boiler pressure loss is being closely monitored. The high steam temperatures (>500 deg. C) of the secondary circuit lead to some decomposition of dimethylamine, which is being carefully monitored at various locations around the circuit. The decomposition products identified with dimethylamine dosing include ammonia, methylamine, formic acid, carbon dioxide and, as yet, unidentified neutral organic species. The effect of dimethylamine dosing on iron transport, boiler pressure drops and its decomposition behaviour around the secondary circuit during the plant trial will be presented in this paper. (authors)

Report of the Federal Ministry for the Environment, Nature Conservation, Buildings and Nuclear Safety (BMUB) on the topical peer review aging management in nuclear power plants and research reactors

International Nuclear Information System (INIS)

2017-01-01

The report of the Federal Environmental Ministry (BMUB) on the topical peer review aging management in nuclear power plants and research reactors covers the following issues: comprehensive requirements for aging management and its implementation, electric cables, non accessible pipes, reactor pressure vessel, calandria/pressure tubes (CANDU), concrete containment, pre-stressed concrete reactor pressure vessel (AGR).

The rate of diffusion into advanced gas cooled reactor moderator bricks: an equivalent cylinder model

International Nuclear Information System (INIS)

Kyte, W.S.

1980-01-01

The graphite moderator bricks which make up the moderator of an advanced gas-cooled nuclear reactor (AGR) are of many different and complex shapes. Many physico-chemical processes that occur within these porous bricks include a diffusional step and thus to model these processes it is necessary to solve the diffusion equation (with chemical reaction) in a porous medium of complex shape. A finite element technique is applied to calculating the rate at which nitrogen diffuses into and out of the porous moderator graphite during operation of a shutdown procedure for an AGR. However, the finite element method suffers from several disadvantages that undermine its general usefulness for calculating rates of diffusion in AGR moderator cores. A model which overcomes some of these disadvantages is presented (the equivalent cylinder model) and it is shown that this gives good results for a variety of different boundary and initial conditions

Radionuclide compositions of spent fuel and high level waste from commercial nuclear reactors

International Nuclear Information System (INIS)

Goodill, D.R.; Tymons, B.J.

1984-10-01

This report provides information on radionuclide compositions of spent fuel and high level waste produced during reprocessing. The reactor types considered are Magnox, AGR, PWR and CFR. The activities of the radionuclides are calculated using the FISPIN code. The results are presented in a form suitable for radioactive waste management calculations. (author)

Antisense locked nucleic acids targeting agrA inhibit quorum sensing and pathogenesis of community-associated methicillin-resistant Staphylococcus aureus.

Science.gov (United States)

Da, F; Yao, L; Su, Z; Hou, Z; Li, Z; Xue, X; Meng, J; Luo, X

2017-01-01

Community-associated methicillin-resistant Staphylococcus aureus (CA-MRSA) is commonly associated with nonnosocomial skin and soft tissue infections due to its virulence, which is mainly controlled by the accessory gene regulator (agr) quorum sensing (QS) system. In this study (KFF) 3 K peptide-conjugated locked nucleic acids (PLNAs) targeting agrA mRNA were developed to inhibit agr activity and arrest the pathogenicity of CA-MRSA. Two PLNAs were designed, and synthesized, after predicting the secondary structure of agrA mRNA. The influence on bacterial growth was tested using a growth curve assay. RT-qPCR, haemolysis assay, lactate dehydrogenase release assay and chemotaxis assay were used to evaluate the effects of the PLNAs on inhibiting agr QS. A mouse skin infection model was employed to test the protective effect of the PLNAs in vivo. None of the PLNAs were found to be bacteriostatic or bactericidal in vitro. However, one PLNA, PLNA34, showed strong ability to suppress expression of agrA and the effector molecule RNAIII in USA300 LAC strain. Furthermore, PLNA34 inhibited the expression of virulence genes that are upregulated by agr, including hla, psmα, psmβ and pvl. The haemolytic activity of the supernatants from PLNA34-treated bacteria was also dramatically reduced, as well as the capacity to lyse and recruit neutrophils. Moreover, PLNA34 showed high levels of protection in the CA-MRSA mouse skin infection model. The anti-agrA PLNA34 can effectively inhibit the agr QS and suppress CA-MRSA pathogenicity. agrA is a promising target for the development of antisense oligonucleotides to block agr QS. Journal of Applied Microbiology © 2016 The Society for Applied Microbiology.

A review of the physics methods for advanced gas-cooled reactors

International Nuclear Information System (INIS)

Buckler, A.N.

1982-01-01

A review is given of steady-state reactor physics methods and associated codes used in AGR design and operation. These range from the basic lattice codes (ARGOSY, WIMS), through homogeneous-diffusion theory fuel management codes (ODYSSEUS, MOPSY) to a fully heterogeneous code (HET). The current state of development of the methods is discussed, together with illustrative examples of their application. (author)

Chitinase expression in Listeria monocytogenes is positively regulated by the Agr system

DEFF Research Database (Denmark)

Paspaliari, Dafni Katerina; Mollerup, Maria Storm; Kallipolitis, Birgitte H.

2014-01-01

The food-borne pathogen Listeria monocytogenes encodes two chitinases, ChiA and ChiB, which allow the bacterium to hydrolyze chitin, the second most abundant polysaccharide in nature. Intriguingly, despite the absence of chitin in human and mammalian hosts, both of the chitinases have been deemed...... important for infection, through a mechanism that, at least in the case of ChiA, involves modulation of host immune responses. In this study, we show that the expression of the two chitinases is subject to regulation by the listerial agr system, a homologue of the agr quorum-sensing system of Staphylococcus...... chitinolytic activity on agar plates. Agr was specifically induced in response to chitin addition in stationary phase and agrD was found to regulate the amount of chiA, but not chiB, transcripts. Although the transcript levels of chiB did not depend on agrD, the extracellular protein levels of both chitinases...

Choice of thermal reactor systems: a report

Energy Technology Data Exchange (ETDEWEB)

1977-09-01

This is a report by the UK National Nuclear Corporation published by the UK Secretary of State for Energy (Mr. Benn) on 29th July 1977. It is concerned with the advantages and disadvantages of three thermal reactor systems -the AGR (advanced gas cooled reactor), the PWR (pressurised water reactor), and the SGHWR (steam generating heavy water reactor). The object was to help in the future choice of a thermal system for the UK to cover the next 25 years. The matter of export potential is also considered. A programme of four stations of 1100 to 1300 MW each over six years starting from 1979 was assumed. It is emphasised that a decision must be taken now both about reactor systems and actual orders. Headings are as follows: Extract from conclusions reached; Summary of main features of assessment; General conclusions regarding the following - safety, security of the investment, operational characteristics, development and launching requirements, effect on industry, and capital and generation costs. It is stated that in order to make an overall judgement on reactor choice the technical, commercial and social issues involved must be weighed in conjunction with cost differentials.

AGR fuel pin pellet-clad interaction failure limits and activity release fractions

International Nuclear Information System (INIS)

Hughes, H.; Hargreaves, R.

1985-01-01

The limiting conditions beyond which pellet-clad interaction can flail AGR fuel are described. They have been determined by many experiments involving post-irradiation examination and testing, loop experiments and cycling and up-rating of both individual fuel stringers and the whole WAGR core. The mechanisms causing this interaction are well understood and are quantitatively expressed in computer codes. Strain concentration effects over fuel cracks determine power cycling endurance while additional strain concentrations at clad ridges and from cross pin temperature gradients contribute to up-rating failures. An equation summarising tube burst test data so as to determine the ductility available at any transient is given. The hollow fuel and more ductile clad of the Civil AGR fuel pins leads to a much improved performance over the original fuel design. The Civil AGRs operate well within these limiting conditions and substantial increases beyond the design burn-up are confidently expected. The activity release on pin failure and its development during continued operation of failed fuel have also been investigated. A retention of radioiodine and caesium of 90-99% compared to the noble gases has been demonstrated. Measured fission gas releases into the free volume of Civil AGR fuel pins have been very low (< 0.1%)

Cross-Talk between Staphylococcus aureus and Other Staphylococcal Species via the agr Quorum Sensing System

DEFF Research Database (Denmark)

Canovas de la Nuez, Jaime; Baldry, Mara; Bojer, Martin S

2016-01-01

-inducing peptides (AIPs) sensed by AgrC, a two component histidine kinase. agr loci are found also in other staphylococcal species and for Staphylococcus epidermidis, the encoded AIP represses expression of agr regulated virulence genes in S. aureus. In this study we aimed to better understand the interaction...... between staphylococci and S. aureus, and show that this interaction may eventually lead to the identification of new anti-virulence candidates to target S. aureus infections. Here we show that culture supernatants of 37 out of 52 staphylococcal isolates representing 17 different species inhibit S. aureus...... suggesting that agr is an inter-species communication system. Based on these results we speculate that interactions between S. aureus and other colonizing staphylococci will significantly influence the ability of S. aureus to cause infection, and we propose that other staphylococci are potential sources...

Listeria monocytogenes differential transcriptome analysis reveals temperature-dependent Agr regulation and suggests overlaps with other regulons.

Science.gov (United States)

Garmyn, Dominique; Augagneur, Yoann; Gal, Laurent; Vivant, Anne-Laure; Piveteau, Pascal

2012-01-01

Listeria monocytogenes is a ubiquitous, opportunistic pathogenic organism. Environmental adaptation requires constant regulation of gene expression. Among transcriptional regulators, AgrA is part of an auto-induction system. Temperature is an environmental cue critical for in vivo adaptation. In order to investigate how temperature may affect AgrA-dependent transcription, we compared the transcriptomes of the parental strain L. monocytogenes EGD-e and its ΔagrA mutant at the saprophytic temperature of 25°C and in vivo temperature of 37°C. Variations of transcriptome were higher at 37°C than at 25°C. Results suggested that AgrA may be involved in the regulation of nitrogen transport, amino acids, purine and pyrimidine biosynthetic pathways and phage-related functions. Deregulations resulted in a growth advantage at 37°C, but affected salt tolerance. Finally, our results suggest overlaps with PrfA, σB, σH and CodY regulons. These overlaps may suggest that through AgrA, Listeria monocytogenes integrates information on its biotic environment.

Review of inspection of Torness reactor internals using remote techniques

International Nuclear Information System (INIS)

Dynan, J.

1993-01-01

Inspection of reactor internals is increasingly being achieved by deployment of cameras into areas of sometimes high radiation fields using manipulators. The manipulators have been developed over a number of years and from a variety of sources and those provided at Torness can maybe be seen to be the state of the art development of such machines for AGRS. Torness and Heysham 2 reactors were specifically designed for inspection using remote techniques and special facilities have been provided for this purpose. This paper is written by an operator and not a manipulator specialist and is intended to show what the operator needs versus what the designer gave him. (author)

Developing equipment for AGR remote visual inspection

International Nuclear Information System (INIS)

James, P.W.; Walton, P.J.

1985-01-01

The Remote Inspection Group is part of the CEGB's Generation Development and Construction Division, and has responsibility for the design, development, procurement, testing and setting to work of the equipment provided to carry out routine remote visual inspections of its AGRs. This equipment includes both the viewing devices and the necessary placement equipment. (author)

Graphites and composites irradiations for gas cooled reactor core structures

International Nuclear Information System (INIS)

Van der Laan, J.G.; Vreeling, J.A.; Buckthorpe, D.E.; Reed, J.

2008-01-01

Full text of publication follows. Material investigations are undertaken as part of the European Commission 6. Framework Programme for helium-cooled fission reactors under development like HTR, VHTR, GCFR. The work comprises a range of activities, from (pre-)qualification to screening of newly designed materials. The High Flux Reactor at Petten is the main test bed for the irradiation test programmes of the HTRM/M1, RAPHAEL and ExtreMat Integrated Projects. These projects are supported by the European Commission 5. and 6. Framework Programmes. To a large extent they form the European contribution to the Generation-IV International Forum. NRG is also performing a Materials Test Reactor project to support British Energy in preparing extended operation of their Advanced Gas-cooled Reactors (AGR). Irradiations of commercial and developmental graphite grades for HTR core structures are undertaken in the range of 650 to 950 deg C, with a view to get data on physical and mechanical properties that enable engineering design. Various C- and SiC-based composite materials are considered for support structures or specific components like control rods. Irradiation test matrices are chosen to cover commercial materials, and to provide insight on the behaviour of various fibre and matrix types, and the effects of architecture and manufacturing process. The programme is connected with modelling activities to support data trending, and improve understanding of the material behaviour and micro-structural evolution. The irradiation programme involves products from a large variety of industrial and research partners, and there is strong interaction with other high technology areas with extreme environments like space, electronics and fusion. The project on AGR core structures graphite focuses on the effects of high dose neutron irradiation and simultaneous radiolytic oxidation in a range of 350 to 450 deg C. It is aimed to provide data on graphite properties into the parameter space

Project WAGR: the UK demonstration project for power reactor decommissioning - a review of the tools used to dismantle the reactor core

International Nuclear Information System (INIS)

Benest, T.G.

2008-01-01

The United Kingdom Atomic Energy Authority (UKAEA) has built and operated a wide range of nuclear facilities since the late 1940. UKAEA mission is to restore the environment of its sites in a safe and secure manner. This restoration includes the decommissioning of a number of redundant research and power reactors. The Windscale Advanced Gas-cooled Reactor (WAGR) was the UK prototype Advanced gas cooled reactor and became the forerunner of a family of 14 reactors built to generate cheaper and more efficient electricity in the UK. WAGR was constructed between 1957 and 1961 and was a carbon dioxide cooled, graphite moderated reactor using uranium oxide fuel in stainless steel cans. The reactor consisted of a graphite moderator housed in a cylindrical reactor vessel with hemispherical ends. The reactor and associated heat exchangers were enclosed in the iconic spherical containment building regularly used by the media in the UK as an illustration of the nuclear industry. The reactor first produced power in August 1962 and achieved full design output in 1963. It operated at an electrical output of 33 MW (E) for 18 years (average load factor of 75%). In 1981 the reactor was shut down after satisfactory completion of all the research and development objectives. In anticipation of the UK likely nuclear decommissioning needs the UKAEA decided to decommission WAGR to the International Atomic Energy Agency (IAEA) stage 3 (restoration of the area occupied by the facility to a condition of unrestricted re-usability) as the national demonstration exercise for power reactor decommissioning. Since 1998 the UKAEA and its contractors have been undertaking the dismantling of the reactor core components and pressure vessel in a series of 10 campaigns. These contain neutron activated components expected to produce dose rates well in excess of 1 Sv/hr. To carry out the work UKAEA installed an 8M remote dismantling machine (RDM) a waste recovery and transport system and a shielded waste

Comércio agrícola: o Brasil e a OMC

Directory of Open Access Journals (Sweden)

Danielle Annoni

2004-03-01

Full Text Available The agricultural and textile sectors, have been the greaters targets of the developed countries protectionism, that possess in common the fact that the amount of man-power used is sufficiently great, it means variation of the products final cost. Therefore, it is not difficult to understand why the most underdeveloped countries are more competitive in the dispute of the world-wide market’s control in these sectors. Thus the importance of the OMC elapses, in the search for the effectiveness of international trade regulation of agricultural goods is an activity that interests the developing countries, what is particularly applicable to Brazil, where the agricultural products answers almost for one third of the exportations.Los sectores agrícolas y textil, han sido los mayores objetivos del proteccionismo de los países desarrollados, que poseen en común la cantidad de mano-de-obra usado y esta energía es suficientemente grande y significa variación del costo final del producto. Por tanto, no es difícil comprender porque cuanto más subdesarrollados los países, más serán competitivos y amenazadores para el conflicto sobre el control del mercado mundial en estos sectores. Así la importancia del OMC transcurre, en la búsqueda para la eficacia de la regulación del comercio internacional de mercancías agrícolas es una, actividad que interesa a los países en vías de desarrollo en su totalidad, lo que es particularmente aplicable al Brasil, donde los productos agrícolas casi contestan para un tercio de las exportaciones.Os setores agrícola e têxtil, têm sido os maiores alvos do protecionismo dos países desenvolvidos, que possuem em comum o fato de que a quantidade de mão-de-obra utilizada é bastante grande o que significa margem de variação do custo final do produto. Portanto, não é difícil entender porque os países quão mais subdesenvolvidos forem mais competitivos e ameaçadores são na disputa pelo controle do mercado

The achievement of on-load refuelling at Heysham 2 and Torness AGRs

International Nuclear Information System (INIS)

Sterland, P.R.; MacPherson, D.

1995-01-01

Heysham 2 and Torness are the last of the advanced gas cooled reactors (AGR) constructed for the Central Electricity Generating Board and the South of Scotland Electricity Board. They are now operated by Nuclear Electric (NE) and Scottish Nuclear Limited (SNL) respectively. They were designed for on load refuelling at high power and being based on the design used for Hinkley Point B and Hunterston B, have benefited from experience at these stations. This paper examines the analysis work which was carried out in order to provide a sound, long term, mainly probabilistic safety case which supports on load refuelling. A significant problem has been that the design reliability of the microprocessor based control and protection systems, used for the fuel route, could not be justified and a number of changes to the overall protection system have had to be introduced to compensate for this. The resultant safety case complies with the stringent safety standards adopted by NE and SNL and accepted by the UK safety authority, the Nuclear Installations Inspectorate (NII). (author)

O Brasil agrícola: o tortuoso e difícil “caminho da roça”

Directory of Open Access Journals (Sweden)

João Klug

2016-01-01

Full Text Available Brasil atualmente é um dos maiores produtores de commodities agrícolas, tais como soja, café, carne (bovina, suína e de aves, açúcar e suco de laranja, e o país se orgulha disso. Essa é uma realidade que começou com a adoção da Revolução Verde na década de 1960 (alta tecnologia no campo, mecanização, insumos, seleção genética, etc., quando foi implantado um modelo de farmerização. Para se chegar a esse modelo de agricultura, concentrador e pouco democrático, o Brasil precisou de quase cinco séculos. Durante a maior parte desse longo período, a agricultura não era vista como atividade nobre, ao contrário, procurava-se superar a identidade agrária, visto que a atividade não conferia status. Em certa medida, o Brasil teve vergonha de ser agrícola. Neste trabalho, o objetivo é analisar como o Brasil, um país agrário, durante mais de três séculos teve dificuldades de assumir uma identidade agrária, especialmente em função da influência de uma mentalidade portuguesa não afeita às lides agrícolas.

Ceramographic Examinations of Irradiated AGR-1 Fuel Compacts

Energy Technology Data Exchange (ETDEWEB)

Paul Demkowicz; Scott Ploger; John Hunn

2012-05-01

The AGR 1 experiment involved irradiating 72 cylindrical fuel compacts containing tri-structural isotropic (TRISO)-coated particles to a peak burnup of 19.5% fissions per initial metal atom with no in-pile failures observed out of almost 300,000 particles. Five irradiated AGR 1 fuel compacts were selected for microscopy that span a range of irradiation conditions (temperature, burnup, and fast fluence). These five compacts also included all four TRISO coating variations irradiated in the AGR experiment. The five compacts were cross-sectioned both transversely and longitudinally, mounted, ground, and polished after development of careful techniques for preserving particle structures against preparation damage. Approximately 40 to 80 particles within each cross section were exposed near enough to mid-plane for optical microscopy of kernel, buffer, and coating behavior. The microstructural analysis focused on kernel swelling and porosity, buffer densification and fracture, debonding between the buffer and inner pyrolytic carbon (IPyC) layers, and fractures in the IPyC and SiC layers. Three basic particle morphologies were established according to the extent of bonding between the buffer and IPyC layers: complete debonding along the interface (Type A), no debonding along the interface (Type B), and partial debonding (Type AB). These basic morphologies were subdivided according to whether the buffer stayed intact or fractured. The resulting six characteristic morphologies were used to classify particles within each cross section, but no spatial patterns were clearly observed in any of the cross-sectional morphology maps. Although positions of particle types appeared random within compacts, examining a total of 830 classified particles allowed other relationships among morphological types to be established.

Ceramographic Examinations of Irradiated AGR-1 Fuel Compacts

International Nuclear Information System (INIS)

Demkowicz, Paul; Ploger, Scott; Hunn, John

2012-01-01

The AGR 1 experiment involved irradiating 72 cylindrical fuel compacts containing tri-structural isotropic (TRISO)-coated particles to a peak burnup of 19.5% fissions per initial metal atom with no in-pile failures observed out of almost 300,000 particles. Five irradiated AGR 1 fuel compacts were selected for microscopy that span a range of irradiation conditions (temperature, burnup, and fast fluence). These five compacts also included all four TRISO coating variations irradiated in the AGR experiment. The five compacts were cross-sectioned both transversely and longitudinally, mounted, ground, and polished after development of careful techniques for preserving particle structures against preparation damage. Approximately 40 to 80 particles within each cross section were exposed near enough to mid-plane for optical microscopy of kernel, buffer, and coating behavior. The microstructural analysis focused on kernel swelling and porosity, buffer densification and fracture, debonding between the buffer and inner pyrolytic carbon (IPyC) layers, and fractures in the IPyC and SiC layers. Three basic particle morphologies were established according to the extent of bonding between the buffer and IPyC layers: complete debonding along the interface (Type A), no debonding along the interface (Type B), and partial debonding (Type AB). These basic morphologies were subdivided according to whether the buffer stayed intact or fractured. The resulting six characteristic morphologies were used to classify particles within each cross section, but no spatial patterns were clearly observed in any of the cross-sectional morphology maps. Although positions of particle types appeared random within compacts, examining a total of 830 classified particles allowed other relationships among morphological types to be established.

Investigation of thermally sensitised stainless steels as analogues for spent AGR fuel cladding to test a corrosion inhibitor for intergranular stress corrosion cracking

Science.gov (United States)

Whillock, Guy O. H.; Hands, Brian J.; Majchrowski, Tom P.; Hambley, David I.

2018-01-01

A small proportion of irradiated Advanced Gas-cooled Reactor (AGR) fuel cladding can be susceptible to intergranular stress corrosion cracking (IGSCC) when stored in pond water containing low chloride concentrations, but corrosion is known to be prevented by an inhibitor at the storage temperatures that have applied so far. It may be necessary in the future to increase the storage temperature by up to ∼20 °C and to demonstrate the impact of higher temperatures for safety case purposes. Accordingly, corrosion testing is needed to establish the effect of temperature increases on the efficacy of the inhibitor. This paper presents the results of studies carried out on thermally sensitised 304 and 20Cr-25Ni-Nb stainless steels, investigating their grain boundary compositions and their IGSCC behaviour over a range of test temperatures (30-60 °C) and chloride concentrations (0.3-10 mg/L). Monitoring of crack initiation and propagation is presented along with preliminary results as to the effect of the corrosion inhibitor. 304 stainless steel aged for 72 h at 600 °C provided a close match to the known pond storage corrosion behaviour of spent AGR fuel cladding.

Sensitivity Evaluation of the Daily Thermal Predictions of the AGR-1 Experiment in the Advanced Test Reactor

Energy Technology Data Exchange (ETDEWEB)

Grant Hawkes; James Sterbentz; John Maki

2011-05-01

A temperature sensitivity evaluation has been performed for the AGR-1 fuel experiment on an individual capsule. A series of cases were compared to a base case by varying different input parameters into the ABAQUS finite element thermal model. These input parameters were varied by ±10% to show the temperature sensitivity to each parameter. The most sensitive parameters are the outer control gap distance, heat rate in the fuel compacts, and neon gas fraction. Thermal conductivity of the compacts and graphite holder were in the middle of the list for sensitivity. The smallest effects were for the emissivities of the stainless steel, graphite, and thru tubes. Sensitivity calculations were also performed varying with fluence. These calculations showed a general temperature rise with an increase in fluence. This is a result of the thermal conductivity of the fuel compacts and graphite holder decreasing with fluence.

ELECTRON PROBE MICROANALYSIS OF IRRADIATED AND 1600°C SAFETY-TESTED AGR-1 TRISO FUEL PARTICLES WITH LOW AND HIGH RETAINED 110MAG

Energy Technology Data Exchange (ETDEWEB)

Wright, Karen E.; van Rooyen, Isabella J.

2016-11-01

AGR-1 fuel Compact 4-3-3 achieved 18.63% FIMA and was exposed subsequently to a safety test at 1600°C. Two particles, AGR1-433-003 and AGR1-433-007, with measured-to-calculated 110mAg inventories of <22% and 100%, respectively, were selected for comparative electron microprobe analysis to determine whether the distribution or abundance of fission products differed proximally and distally from the deformed kernel in AGR1-433-003, and how this compared to fission product distribution in AGR1-433-007. On the deformed side of AGR1-433-003, Xe, Cs, I, Eu, Sr, and Te concentrations in the kernel buffer interface near the protruded kernel were up to six times higher than on the opposite, non-deformed side. At the SiC-inner pyrolytic carbon (IPyC) interface proximal to the deformed kernel, Pd and Ag concentrations were 1.2 wt% and 0.04 wt% respectively, whereas on the SiC-IPyC interface distal from the kernel deformation those elements measured 0.4 and 0.01 wt%, respectively. Palladium and Ag concentrations at the SiC-IPyC interface of AGR1-433-007 were 2.05 and 0.05 wt.%, respectively. Rare earth element concentrations at the SiC-IPyC interface of AGR1-433-007 were a factor of ten higher than at the SiC-IPyC interfaces measured in particle AGR1-433-003. Palladium permeated the SiC layer of AGR1-433-007 and the non-deformed SiC layer of AGR1-433-003.

Sistemas de producción agrícola sostenible

Directory of Open Access Journals (Sweden)

Róger Martínez Castillo

2009-01-01

Full Text Available El desarrollo sostenible se fundamenta en principios éticos, como el respeto y armonía con la naturaleza; valores políticos, como la democracia participativa y equidad social; y normas morales, como racionalidad ambiental. El desarrollo sostenible es igualitario, descentralizado y autogestionario, capaz de satisfacer las necesidades básicas de la población, respetando la diversidad cultural y mejorando la calidad de vida. La agricultura y el desarrollo sostenible se refieren a la necesidad de minimizar la degradación de la tierra agrícola, maximizando a su vez la producción. Este considera el conjunto de las actividades agrícolas, como el manejo de suelos y aguas,el manejo de cultivos y la conservación de la biodiversidad; considerando a su vez el suministro de alimentos y materias primas. La sostenibilidad de los sistemas de producción agrícola se refiere a la capacidad del sistema para mantener su productividad a pesar de las perturbaciones económicas y naturales, externas o internas. La sostenibilidad es función de las características naturales del sistema y las presiones e intervenciones que sufre, así como aquellas intervenciones sociales, económicas y técnicas que se hacen para contrarrestar presiones negativas; destacándose la resiliencia del sistema.

Modelos de vulnerabilidad agrícola ante los efectos del cambio climático

Directory of Open Access Journals (Sweden)

Claudia Hernández Ramírez

2014-12-01

Full Text Available La Vulnerabilidad Agrícola (VA es el resultado de la medición de la variabilidad climática dentro de un contexto de vulnerabilidad social y sectorial, que ha ido agregando conceptos e indicadores que enriquecen y complementan el análisis de la seguridad alimentaria, en el entendido que la disponibilidad de un pronóstico corresponde no solo al derecho primordial de cualquier ser humano, sino a la supervivencia del mismo. La metodología de medición de esta variable depende estrictamente del alcance de la investigación y de la disponibilidad de datos de la región y del producto agrícola seleccionado. Los modelos utilizados hasta la fecha son tres: el modelo Estructural, el modelo Espacial y la Vulnerabilidad Agrícola.

A Revolução Agrária Cubana: conquistas e desafios

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Juan Valdés Paz

2011-01-01

Full Text Available Após o triunfo da Revolução em 1959, iniciou-se uma profunda transformação da sociedade cubana, primeiro política, depois social e, desde muito cedo, agrária. A Revolução Cubana foi a superação da questão agrária originada na etapa republicana e uma opção socialista para o desenvolvimento socioeconômico do país, do qual o desenvolvimento agrário tem sido um eixo fundamental. A superação dessa "questão agrária" do socialismo cubano determina as estratégias em curso e suas metas imediatas. Como parte desse processo, examinamos seis aspectos que caracterizaram seu desenvolvimento; são eles: a estrutura da pose de terra; o uso do solo; a organização agrária; o modelo tecnológico; a economia agrária; e o desenvolvimento da sociedade rural.Con el triunfo de la Revolución en 1959, se inició una profunda transformación de la sociedad cubana, primero política, después social y desde muy tempranamente, agraria. La Revolución Cubana fue la superación de la cuestión agraria originada en la etapa republicana y una opción socialista para el desarrollo socioeconómico del país, del cual el desarrollo agrario ha sido un eje fundamental. La superación de esta "cuestión agraria" del socialismo cubano, determina las estrategias en curso y sus metas inmediatas. Como parte de ese proceso, se examinan seis de los aspectos que caracterizaron su desarrollo, a saber: la estructura de tenencia de la tierra; el uso del suelo; la organización agraria; el modelo tecnológico; la economía agraria; y el desarrollo de la sociedad rural.After the triumph of the revolution in 1959, a profound transformation of Cuban society began - first political, then social and, very early on, agrarian. The Cuban Revolution surmounted the agrarian issue that had originated during the republican phase and embodied a socialist option for socioeconomic development (of which agricultural development was a fundamental part. Cuban socialism's efforts to

Green Fluorescent Protein (GFP-Based Overexpression Screening and Characterization of AgrC, a Receptor Protein of Quorum Sensing in Staphylococcus aureus

Directory of Open Access Journals (Sweden)

Shengdi Fan

2013-09-01

Full Text Available Staphylococcus aureus AgrC is an important component of the agr quorum-sensing system. AgrC is a membrane-embedded histidine kinase that is thought to act as a sensor for the recognition of environmental signals and the transduction of signals into the cytoplasm. However, the difficulty of expressing and purifying functional membrane proteins has drastically hindered in-depth understanding of the molecular structures and physiological functions of these proteins. Here, we describe the high-yield expression and purification of AgrC, and analyze its kinase activity. A C-terminal green fluorescent protein (GFP fusion to AgrC served as a reporter for monitoring protein expression levels in real time. Protein expression levels were analyzed by the microscopic assessment of the whole-cell fluorescence. The expressed AgrC-GFP protein with a C-terminal His-tagged was purified using immobilized metal affinity chromatography (IMAC and size exclusion chromatography (SEC at yields of ≥10 mg/L, following optimization. We also assessed the effects of different detergents on membrane solubilization and AgrC kinase activity, and polyoxyethylene-(23-lauryl-ether (Brij-35 was identified as the most suitable detergent. Furthermore, the secondary structural stability of purified AgrC was analyzed using circular dichroism (CD spectroscopy. This study may serve as a general guide for improving the yields of other membrane protein preparations and selecting the appropriate detergent to stabilize membrane proteins for biophysical and biochemical analyses.

A Review of the United Kingdom Fast Reactor Programme, March 1987

International Nuclear Information System (INIS)

Bramman, J.I.; Wheeler, R.C.

1987-01-01

Nuclear power produced about 20% of the electricity supply in the United Kingdom in 1986, mostly from gas-cooled reactors, i.e. the 10 AGRs currently in operation and the 26 older MAGNOX reactors. Plans to increase the nuclear component of generating capacity by building the first PWR in the UK, Sizewell 'B', were strongly endorsed in the report by Sir Frank Layfield published on 26 January 1987. This resulted from the Public Inquiry into building Sizewell 'B', which was held between 11 January 1983 and 7 March 1985, the longest Public Inquiry ever held in the UK. The government gave the go-ahead for the building of Sizewell 'B' on 12 March 1987

Diagnósticos de las apuestas productivas para seis productos del sector agrícola en Colombia

OpenAIRE

Quintero Rubio, Paula Vanesa; Rubio Rodriguez, Juan Camilo

2014-01-01

El documento “Diagnósticos de las apuestas productivas para seis productos del sector agrícola en Colombia”, pretende proporcionar herramientas para el incremento productivo de seis productos agrícolas con un alto potencial en el país, mediante la identificación de mercados internacionales factibles, el análisis de sus procesos de producción y la comparación de eficiencia en costos del transporte de mercancía a nivel nacional; buscando el aumento de la participación del PIB agrícola en el PI...

Programa computacional para calcular a potência requerida de máquinas e implementos agrícolas

OpenAIRE

Pablo Pereira Corrêa Klaver; Ricardo Ferreira Garcia; José Francisco Sá Vasconcelos Júnior; Delorme Corrêa Junior; Wellington Gonzaga Vale

2013-01-01

O uso de programas computacionais no setor agrícola permite atingir objetivos específicos na área. Dentre esses, um dos mais complexos é a seleção adequada de máquinas e implementos agrícolas visando à otimização de operações agrícolas, devido, principalmente, à grande variedade de equipamentos existentes no mercado e a gama de tarefas e situações de trabalho que estas são submetidas no campo. O objetivo deste trabalho foi desenvolver um programa computacional para calcular a potência requeri...

A Review of the UK Fast Reactor Programme: March 1980

International Nuclear Information System (INIS)

Smith, R.D.

1980-01-01

Towards the end of 1979 the Government announced a new programme of thermal reactor stations to be built over ten years (totalling 15GW), in addition to the two AGR stations at Torness and Heysham 'B' which had been approved by the previous Government. The first station of the new programme will be based on a Westinghouse PWR, subject to safety clearance and the outcome of a public inquiry, and it is envisaged that the remaining stations of the programme would be split between PWRs and AGRs. The AEA Chairman wrote formally to the Secretary of State for Energy in December 1979, putting forward on behalf of the Electricity Supply Authorities, NNC, BNFL and the AEA a recommended strategy for building the Commercial Demonstration Fast Reactor (CDFR), subject to normal licensing procedure and to public inquiry, so as to ensure that the key options for introducing commercial fast reactors, when required, should remain open. A Government statement is expected during the next few months. Meanwhile the level of effort on fast reactor research and development in the UK has been maintained, the fast reactor remaining the largest of the UKAEA's reactor development projects with expenditure totalling somewhat over £80M per annum. The main feature of the UK fast reactor programme has continued to be the operation of PFR (Sections 2 and 7) which is yielding a wealth of experience and of information relevant to the design of commercial fast reactors. Bum-up of standard driver fuel has reached 6-7% by heavy atoms, while specially enriched lead fuel pins have reached 11 % without failure. An extensive programme of work in the reactor and its associated steam plant was completed in March 1980 and the reactor then started its fifth power run. The fuel reprocessing plant at DNE is being commissioned and has reprocessed some of the spent fuel remaining from the DFR. It will start soon on reprocessing fuel discharged from the PFR. During the year improvements to the design of the future

Programa computacional para calcular a potência requerida de máquinas e implementos agrícolas

Directory of Open Access Journals (Sweden)

Pablo Pereira Corrêa Klaver

2013-12-01

Full Text Available O uso de programas computacionais no setor agrícola permite atingir objetivos específicos na área. Dentre esses, um dos mais complexos é a seleção adequada de máquinas e implementos agrícolas visando à otimização de operações agrícolas, devido, principalmente, à grande variedade de equipamentos existentes no mercado e a gama de tarefas e situações de trabalho que estas são submetidas no campo. O objetivo deste trabalho foi desenvolver um programa computacional para calcular a potência requerida de máquinas e implementos agrícolas normalmente utilizados na condução de operações de campo, desde o preparo do solo até as operações de implantação de culturas. Desenvolvido em linguagem PHP, o programa computacional baseia-se na norma ASAE D497.4 - Agricultural Machinery Management Data como referência para desenvolvimento de cálculos. A partir do programa desenvolvido, tornou-se possível a execução de tarefas para cálculos de avaliação da demanda de potência de máquinas e implementos agrícolas de forma simplificada pela internet.

A safety assessment of the use of graphite in nuclear reactors licensed by the US NRC

International Nuclear Information System (INIS)

Schweitzer, D.G.; Gurinsky, D.H.; Kaplan, E.; Sastre, C.

1987-09-01

This report reviews existing literature and knowledge on graphite burning and on stored energy accumulation and releases in order to assess what role, if any, a stored energy release can have in initiating or contributing to hypothetical graphite burning scenarios in research reactors. It also addresses the question of graphite ignition and self-sustained combustion in the event of a loss-of-coolant accident (LOCA). The conditions necessary to initiate and maintain graphite burning are summarized and discussed. From analyses of existing information it is concluded that only stored energy accumulations and releases below the burning temperature (650 0 C) are pertinent. After reviewing the existing knowledge on stored energy it is possible to show that stored energy releases do not occur spontaneously, and that the maximum stored energy that can be released from any reactor containing graphite is a very small fraction of the energy produced during the first few minutes of a burning incident. The conclusions from these analyses are that the potential to initiate or maintain a graphite burning incident is essentially independent of the stored energy in the graphite, and depends on other factors that are unique for these reactors, research reactors, and for Fort St. Vrain. In order to have self-sustained rapid graphite oxidation in any of these reactors, certain necessary conditions of geometry, temperature, oxygen supply, reaction product removal, and a favorable heat balance must be maintained. There is no new evidence associated with either the Windscale Accident or the Chernobyl Accident that indicates a credible potential for a graphite burning accident in any of the reactors considered in this review

Specialists' meeting on gas-cooled reactor core and high temperature instrumentation, Windermere, UK, 15-17 June 1982. Summary report

International Nuclear Information System (INIS)

1982-09-01

The Specialists' Meeting on ''Gas-Cooled Reactor Core and High Temperature Instrumentation'' was held at the Beech Hill Hotel, Windermere in England on June 15-17 1982. The meeting was sponsored by the IAEA on the recommendation of the International Working Group on Gas Cooled Reactors and was hosted by the Windscale Nuclear Power Development Laboratories of the UKAEA. The meeting was attended by 43 participants from Belgium, France, Federal Republic of Germany, Japan, United Kingdom of Great Britain and Northern Ireland and the United States of America. The objective of the meeting was to provide a forum, both formal and informal, for the exchange and discussion of technical information relating to instrumentation being used or under development for the measurement of core parameters, neutron flux, temperature, coolant flow etc. in gas cooled reactors. The technical part of the meeting was divided into five subject sessions: (A) Temperature Measurement (B) Neutron Detection Instrumentation (C) HTR Instrumentation - General (D) Gas Analysis and Failed Fuel Detection (E) Coolant Mass Flow and Leak Detection. A total of twenty-five papers were presented by the participants on behalf of their organizations during the meeting. A programme of the meeting and list of participants are given in appendices to this report

PRAPRAG: software para planejamento racional de máquinas agrícolas

OpenAIRE

Mercante,Erivelto; Souza,Eduardo G. de; Johann,Jerry A; Gabriel Filho,Antonio; Uribe-Opazo,Miguel A

2010-01-01

O software PRAPRAG é uma ferramenta de escolha de máquinas e implementos agrícolas que apresentam o menor custo por área ou por quantidade produzida, bem como, faz o planejamento de aquisição das máquinas para a propriedade agrícola, do ponto de vista técnico e econômico. Foi utilizada a linguagem de programação Borland Delphi 3.0 e, a partir de prospectos das máquinas e implementos, criou-se um banco de dados onde o usuário pode cadastrar e modificar suas características de uso. O software m...

ART Or AGR: Deciphering Which Reserve Program is Best Suited for Today’s Total Force Structure

Science.gov (United States)

2016-02-01

AIR COMMAND AND STAFF COLLEGE AIR UNIVERSITY ART OR AGR: DECIPHERING WHICH RESERVE PROGRAM IS BEST SUITED FOR TODAY’S TOTAL FORCE STRUCTURE...4 ART Program...time workforce, which are the ART and AGR programs, by comparing each and highlighting the differences, advantages and disadvantages they present to

MODELING AND ANALYSIS OF FISSION PRODUCT TRANSPORT IN THE AGR-3/4 EXPERIMENT

Energy Technology Data Exchange (ETDEWEB)

Humrickhouse, Paul W.; Collin, Blaise P.; Hawkes, Grant L.; Harp, Jason M.; Demkowicz, Paul A.; Petti, David A.

2016-11-01

In this work we describe the ongoing modeling and analysis efforts in support of the AGR-3/4 experiment. AGR-3/4 is intended to provide data to assess fission product retention and transport (e.g., diffusion coefficients) in fuel matrix and graphite materials. We describe a set of pre-test predictions that incorporate the results of detailed thermal and fission product release models into a coupled 1D radial diffusion model of the experiment, using diffusion coefficients reported in the literature for Ag, Cs, and Sr. We make some comparisons of the predicted Cs profiles to preliminary measured data for Cs and find these to be reasonable, in most cases within an order of magnitude. Our ultimate objective is to refine the diffusion coefficients using AGR-3/4 data, so we identify an analytical method for doing so and demonstrate its efficacy via a series of numerical experiments using the model predictions. Finally, we discuss development of a post-irradiation examination plan informed by the modeling effort and simulate some of the heating tests that are tentatively planned.

Necesidades educacionales sobre riesgo de plaguicidas en el contexto socio-ambiental de las comunidades agrícolas de Sonora

OpenAIRE

M.I. Silveira Gramont; L. Aldana Madrid; A.I. Valenzuela Quintanar; C.B. Ochoa Nogales; G. Jasa-Silveira; Beatriz Camarena Gómez

2016-01-01

Para proponer estrategias de educación y comunicación sobre plaguicidas en las comunidades agrícolas de Sonora, se requiere situar la problemática de la exposición a plaguicidas en el contexto socio-cultural y ambiental de las comunidades afectadas, tomando en cuenta los factores que contribuyen al mayor riesgo de exposición de los trabajadores agrícolas y de sus familias. Este estudio examina los factores poblacionales, educacionales, culturales y de trabajo de habitantes y trabajadores agrí...

Report of the Federal Ministry for the Environment, Nature Conservation, Buildings and Nuclear Safety (BMUB) on the topical peer review aging management in nuclear power plants and research reactors; Bericht des Bundesministeriums fuer Umwelt, Naturschutz, Bau und Reaktorsicherheit (BMUB) zum Topical Peer Review Alterungsmanagement in Kernkraftwerken und Forschungsreaktoren

Energy Technology Data Exchange (ETDEWEB)

NONE

2017-12-28

The report of the Federal Environmental Ministry (BMUB) on the topical peer review aging management in nuclear power plants and research reactors covers the following issues: comprehensive requirements for aging management and its implementation, electric cables, non accessible pipes, reactor pressure vessel, calandria/pressure tubes (CANDU), concrete containment, pre-stressed concrete reactor pressure vessel (AGR).

O impacto do trabalho infantil no setor agrícola sobre a saúde

Directory of Open Access Journals (Sweden)

Alexandre Chibebe Nicolella

2008-09-01

Full Text Available O objetivo desse artigo é verificar se o trabalho infantil no setor agrícola produz impacto negativo sobre a saúde. Para a análise foram utilizadas as PNADs (Pesquisas Nacionais por Amostra de Domicílios de 1998 e 2003, que trazem suplemento especial sobre saúde, empregando a técnica econométrica de pseudo-painel. Assim, foram consideradas as crianças de 5 a 15 anos em 1998 e de 10 a 20 anos em 2003. Os resultados mostram que, para os indivíduos economicamente ativos, a atividade no setor agrícola e o trabalho de risco no setor agrícola não diferem dos outros setores, ou seja, trabalhar no setor agrícola não impõe um maior desgaste à saúde em relação aos outros setores da economia. Se considerados todos os indivíduos economicamente ativos, os resultados mostram que o trabalho agrícola não afeta a saúde e que o trabalho não-agrícola tem impacto negativo. Dessa forma, acredita-se que a atuação do governo deve ser setorial, visando uma melhoria no acesso ao sistema de saúde, bem como aos medicamentos, e a promoção da educação materna com relação à saúde.The aim of this dissertation is to identify the causal relation between rural child labour and health. The analysis utilized the PNAD, a Brazilian household survey, from 1998 and 2003. The econometric modeling was based on the pseudo-panel approach and was considered the children from 5 to 15 years old in 1998 and from 10 to 20 years old in 2003. The results show that work and work in risky jobs in the agricultural sector do not differ from those impacts of other sectors. It was also presented, for all individuals that work in the agricultural sector does not impact the health capital and work in the non rural sector impact negatively the health capital. So, the government intervention in rural areas should be different from the one implemented on the urban area to mitigate the impact of child labour on health and also, the government intervention should be

Medium temperature carbon dioxide gas turbine reactor

International Nuclear Information System (INIS)

Kato, Yasuyoshi; Nitawaki, Takeshi; Muto, Yasushi

2004-01-01

A carbon dioxide (CO 2 ) gas turbine reactor with a partial pre-cooling cycle attains comparable cycle efficiencies of 45.8% at medium temperature of 650 deg. C and pressure of 7 MPa with a typical helium (He) gas turbine reactor of GT-MHR (47.7%) at high temperature of 850 deg. C. This higher efficiency is ascribed to: reduced compression work around the critical point of CO 2 ; and consideration of variation in CO 2 specific heat at constant pressure, C p , with pressure and temperature into cycle configuration. Lowering temperature to 650 deg. C provides flexibility in choosing materials and eases maintenance through the lower diffusion leak rate of fission products from coated particle fuel by about two orders of magnitude. At medium temperature of 650 deg. C, less expensive corrosion resistant materials such as type 316 stainless steel are applicable and their performance in CO 2 have been proven during extensive operation in AGRs. In the previous study, the CO 2 cycle gas turbomachinery weight was estimated to be about one-fifth compared with He cycles. The proposed medium temperature CO 2 gas turbine reactor is expected to be an alternative solution to current high-temperature He gas turbine reactors

Modelagem matemática para seleção de conjuntos mecanizados agrícolas pelo menor custo operacional

OpenAIRE

Baio,Fábio H. R.; Rodrigues,Andrew D.; Santos,Gilson S. dos; Silva,Simone P. da

2013-01-01

A seleção de uma máquina agrícola pode tornar-se uma tarefa árdua, pois há diversas variáveis que devem ser consideradas. A escolha do equipamento mais adequado para uma propriedade agrícola é uma das etapas mais importantes do processo produtivo. O objetivo deste trabalho foi desenvolver um modelo de computador por programação linear em plataforma web para seleção automatizada de conjuntos mecanizados agrícolas, baseados no menor custo operacional. O programa, desenvolvido em linguagem ASP.N...

Linear peptidomimetics as potent antagonists of Staphylococcus aureus agr quorum sensing

DEFF Research Database (Denmark)

Karathanasi, Georgia; Bojer, Martin Saxtorph; Baldry, Mara

2018-01-01

Staphylococcus aureus is an important pathogen causing infections in humans and animals. Increasing problems with antimicrobial resistance has prompted the development of alternative treatment strategies, including antivirulence approaches targeting virulence regulation such as the agr quorum...

Comparison of fission product release predictions using PARFUME with results from the AGR-1 irradiation experiment

International Nuclear Information System (INIS)

Collin, Blaise P.; Petti, David A.; Demkowicz, Paul A.; Maki, John T.

2014-01-01

The PARFUME (PARticle FUel ModEl) code was used to predict fission product release from tristructural isotropic (TRISO) coated fuel particles and compacts during the first irradiation experiment (AGR-1) of the Advanced Gas Reactor Fuel Development and Qualification program. The PARFUME model for the AGR-1 experiment used the fuel compact volume average temperature for each of the 620 days of irradiation to calculate the release of fission products silver, cesium, and strontium from a representative particle for a select number of AGR-1 compacts. Post-irradiation examination (PIE) measurements provided data on release of fission products from fuel compacts and fuel particles, and retention of fission products in the compacts outside of the silicon carbide (SiC) layer. PARFUME-predicted fractional release of these fission products was determined and compared to the PIE measurements. Results show an overall over-prediction of the fractional release of cesium by PARFUME. For particles with failed SiC layers, the over-prediction is by a factor of about two, corresponding to an over-estimation of the diffusivity in uranium oxycarbide (UCO) by a factor of about 100. For intact particles, whose release is much lower, the over-prediction is by an average of about an order of magnitude, which could additionally be attributed to an over-estimated diffusivity in SiC by about 30%. The release of strontium from intact particles is also over-estimated by PARFUME, which also points towards an over-estimated diffusivity of strontium in either SiC or UCO, or possibly both. The measured strontium fractional release from intact particles varied considerably from compact to compact, making it difficult to assess the effective over-estimation of the diffusivities. Furthermore, the release of strontium from particles with failed SiC is difficult to observe experimentally due to the release from intact particles, preventing any conclusions to be made on the accuracy or validity of the

Fire safety in atomic power plants

International Nuclear Information System (INIS)

Kench, R.L.; British Insurance

1988-01-01

The main reactor types are described briefly - Magnox, advanced gas cooled, pressurized water and fast reactors. Fire risks exist at fuel stores and spent fuel storage facilities. Simple fire prevention measures are suggested. Solid radioactive wastes can also be combustible. Various fire prevention measures for the different storage methods, eg compaction, are given. Gaseous and liquid wastes are also considered. The main types of reactor accident are described and the causes of four incidents - at Chernobyl, Windscale, Brownsferry and Three Mile Island, are examined. (U.K.)

Some applications of capacitance technology in nuclear reactor components inspections

International Nuclear Information System (INIS)

Walton, H.

1985-01-01

The paper considers application of a capacitance measuring system that has overcome many of the original contraints, such as sensitivity to cable length, induced electric field and high acoustic noise, and illustrates the ease of use with examples of proven capability in severe environments of high temperature or high radiation. The Capacitance Displacement Transducer (CDT) measuring principle was originally developed as a working technique during the early years of full-scale, on-load refuelling trials performed in the Windscale Civil Advanced Gas-Cooled Reactor (CAGR) test rig where it was necessary to measure the vibrational behaviour of fuel components in simulated reactor conditions. At that time, 1968-1969, no instrumentation existed that would measure displacement in the range 0 to 100 mms to an accuracy of 25x10 -3 mms, without physical contact, at temperatures of 600 0 C in high velocity gas, in high acoustic noise fields of 150 db's over cable lengths approaching 100 metres. The principles incorporated in the CDT overcome all these problems. The advantages inherent in this system have been extended to metrology applications in more recent years by the further development of the electronics to enable linear displacement measurement to be obtained between two capacitance plates whose separation varies, either by plate movement or by surface irregularity. This principle has been used to good effect in novel applications associated with the inspection of nominally inaccessible internal tube surfaces

Propuesta para llevar al espacio académico institucional, saberes agrícolas tradicionales

OpenAIRE

Gómez Espinoza, José Antonio

2007-01-01

Este texto se presentó como comunicación al II Congreso Internacional de Etnografía y Educación: Migraciones y Ciudadanías. Universidad Autónoma de Barcelona, Barcelona, 5-8 Septiembre 2008. Mientras en las “milpas” campesinas se practican saberes agrícolas tradicionales (SAT) para la subsistencia campesina a través de la producción de maíz y cultivos asociados (milpa), en las Instituciones de Enseñanza Agrícola Superior del país, se enseña un enorme bagaje científico y tecnológico sin con...

The Choice of thermal reactor systems. A report by the National Nuclear Corporation Limited

International Nuclear Information System (INIS)

1977-01-01

The report to the Secretary of State in Great Britain by the National Nuclear Corporation following their assessment of the three thermal reactor systems, the AGR, PWR and SGHWR type reactors, which was performed in order to assist in the decision on the choice of thermal reactors for the U.K., is in three parts. Part I is an assessment of the three systems. It comprises: a description of the general method of assessment; a commentary in which are summarised discussions on the most important issues influencing reactor choice, i.e. safety, component failure, operational characteristics, development programme, construction programme; implications for the U.K. industry; costs; and reference design of each system. Part II consists of related questions and answers accompanied by commentaries on public acceptability and views from industry. Part III contains some conclusions including an analysis on the implications of the choices open and a summary of the main features of the assessment. (U.K.)

Profissão, escola e campo: um estudo sobre o Ensino Técnico Agrícola

OpenAIRE

Martins-Salandim, Maria Ednéia [UNESP; Garnica, Antonio Vicente Marafioti [UNESP

2010-01-01

Apresentando uma síntese histórico-sociológica do panorama rural brasileiro, da constituição do ensino técnico, e do desenvolvimento do ensino técnico agrícola, este artigo defende que as escolas técnicas agrícolas sofrem uma dupla marginalização, por um lado proveniente de sua natureza profissionalizante e, por outro, dada sua vinculação com o meio rural brasileiro.

Impactos do Protocolo de Cartagena sobre o Comércio de Commodities Agrícolas

OpenAIRE

Borges, Izaías de Carvalho; Silveira, Jose Maria Ferreira Jardim da; Vieira Filho, José Eustáquio; Pereira, Andrea M.

2015-01-01

O Protocolo de Cartagena sobre Biossegurança é um acordo ambiental que agrega 132 países. O Protocolo tem impactos sobre o comércio de commodities agrícolas, porque estabelece regras para o transporte entre fronteiras de organismos vivos modificados (OVMs). O Artigo 18.2(a) do Protocolo refere-se às formas de identificação dos OVMs nos carregamentos de commodities agrícolas. O fato de que os principais países exportadores de grãos também sejam produtores de cultivares geneticamente modificado...

A “questão agrária” em Mariátegui

Directory of Open Access Journals (Sweden)

Frederico Daia Firmiano

2012-05-01

Full Text Available Neste breve artigo temos como objetivo refletir sobre a “questão agrária” no pensamento de José Carlos Mariátegui, sobretudo a partir de sua principal obra, os “Sete ensaios de interpretação da realidade peruana”. Nosso argumento é que o socialista peruano não tratou os problemas da formação social peruana a partir da chave teórica dada pela “questão agrária”, mas a encontrou no curso de uma interpretação marxista, profundamente original e inventiva, sobre esta formação social (desenvolvida ao lado da intensa militância política, identificando o problema indígena ao problema da terra, aos que Amauta conferiu uma alternativa socialista.

La Ingeniería Agrícola en el País

Directory of Open Access Journals (Sweden)

Bustamante M. Hellodoro

1985-12-01

Full Text Available Es sumamente difícil situar en la historia, el origen de la Ingeniería Agrícola, aunque podría remontarse al propio origen de la tierra, de las plantas y de las aguas. La Ingeniería Agrícola está ocupando un campo de acción que se ha desarrollado a pesar de las limitaciones que le ofrece el mismo desarrollo del país y al escepticismo sin fundamento de algunos pregoneros del pesimismo nacional; le corresponde enfrentar además hoy al cáncer del desempleo y a la falta de oportunidad para demostrar al país que la inversión hecha por el estado en la formación de estos profesionales es productiva.

El Título de Ingeniero Agrónomo

Directory of Open Access Journals (Sweden)

Universidad Nacional de Colombia Facultad de Agronomía

1941-08-01

Full Text Available Como es ocurrencia frecuente la controversia sobre la propiedad académica o el derecho que asiste a los profesionales que han cursado estudios superiores de Agronomía para usar el título de Ingenieros Agrónomos, es procedente aclarar este punto sobre todo hoy que en Colombia la carrera agronómica está ocupando destacada posición en el panorama social y económico del país.

Microscopic analysis of irradiated AGR-1 coated particle fuel compacts

Energy Technology Data Exchange (ETDEWEB)

Ploger, Scott A., E-mail: scott.ploger@inl.gov [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3855 (United States); Demkowicz, Paul A. [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, ID 83415-3855 (United States); Hunn, John D.; Kehn, Jay S. [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6093 (United States)

2014-05-01

The AGR-1 experiment involved irradiation of 72 TRISO-coated particle fuel compacts to a peak compact-average burnup of 19.5% FIMA with no in-pile failures observed out of 3 × 10{sup 5} total particles. Irradiated AGR-1 fuel compacts have been cross-sectioned and analyzed with optical microscopy to characterize kernel, buffer, and coating behavior. Six compacts have been examined, spanning a range of irradiation conditions (burnup, fast fluence, and irradiation temperature) and including all four TRISO coating variations irradiated in the AGR-1 experiment. The cylindrical specimens were sectioned both transversely and longitudinally, then polished to expose from 36 to 79 individual particles near midplane on each mount. The analysis focused primarily on kernel swelling and porosity, buffer densification and fracturing, buffer–IPyC debonding, and fractures in the IPyC and SiC layers. Characteristic morphologies have been identified, 981 particles have been classified, and spatial distributions of particle types have been mapped. No significant spatial patterns were discovered in these cross sections. However, some trends were found between morphological types and certain behavioral aspects. Buffer fractures were found in 23% of the particles, and these fractures often resulted in unconstrained kernel protrusion into the open cavities. Fractured buffers and buffers that stayed bonded to IPyC layers appear related to larger pore size in kernels. Buffer–IPyC interface integrity evidently factored into initiation of rare IPyC fractures. Fractures through part of the SiC layer were found in only four classified particles, all in conjunction with IPyC–SiC debonding. Compiled results suggest that the deliberate coating fabrication variations influenced the frequencies of IPyC fractures and IPyC–SiC debonds.

Sostenibilidad de sistemas agrícolas Sustainability of farming systems

Directory of Open Access Journals (Sweden)

Leiva Fabio R.

1998-12-01

Full Text Available Las actividades agrícolas pueden tener impactos negativos sobre el ambiente, con efectos dentro y fuera de los predios. El presente artículo pretende contribuir al avance de la agricultura sostenible con énfasis en países en vías de desarrollo. Se revisan y analizan los conceptos de sostenibilidad y agricultura sostenible, incluyendo los diferentes puntos de vista en el debate sobre sostenibilidad'. El artículo examina los impactos ambientales debidos a las actividades agrícolas, destacando la importancia de fortalecer la investigación, con publicación de resultados, sobre la relación agricultura y medio ambiente. La complejidad de los factores que determinan la sostenibilidad agrícola exige una concepción de sistemas, integradora, participativa y holística. El uso de indicadores tiene un gran potencial en la evaluación de la sostenibilidad de sistemas productivos. La práctica de agricultura sostenible requiere tener en cuenta las condiciones ambientales, sociales y económicas en las cuales
se desenvuelve la agricultura.Farming activities have the potential to affect the farming system itself and the offfarm environment. This paper attempts to contribute to the development of sustainable agriculture with emphasis in developing countries. The concepts of sustainability and sustainable agriculture are reviewed and discussed, including the different viewpoints in the sustainability debate. Environmental impacts due to farming activities are examined emphasising the need of promoting further research and publication of findings on the links between environment and agriculture. The complexity of the factors that determine farming sustainability requires
a systematic, holistic, participative and integrated approach. Indicators are likely to contribute to the development of sustainable farming systems. Understanding environmental, social and economic circumstances is required to promote sustainability.

Puesta en Valor del Patrimonio Agrícola en Ciudades Intermedias, caso Chillán

Directory of Open Access Journals (Sweden)

Marcela Andrea Soto Caro

2016-12-01

Full Text Available Frente al actual escenario territorial, donde la ruralidad persiste en todas sus expresiones identitarias, sociales y económicas, el suelo agrícola pierde extensión, en una pugna constante por sobreponerse a la expansión urbana. Las modificaciones estructurales del espacio periurbano en las últimas décadas nos presentan la consolidación de los procesos de crecimiento y transformación urbana desiguales, que bajo el modelo neoliberal imperante y persistente, se hacen cada vez más visibles en las ciudades de rango intermedio. Si bien no tienen la escala metropolitana, adquieren velocidades de crecimiento urbano aún mayores. El presente estudio compara la evolución de indicadores relacionados con el desarrollo urbano del territorio, para analizar las dinámicas de crecimiento y la pérdida de suelo agrícola. Si bien las ciudades de rango intermedio promueven el consumo de suelo urbano, existe una oportunidad de resaltar el valor patrimonial y productivo del suelo agrícola.

Corrosion studies of thermally sensitised AGR fuel element brace in pH7 and pH9.2 borate solutions

International Nuclear Information System (INIS)

Tyfield, S.P.; Smith, C.A.

1987-04-01

Brace and cladding of AGR fuel elements sensitised in reactor are susceptible to intergranular and crevice corrosion, which may initiate in the pH7 borate pond storage environment of CEGB/SSEB stations. This report considers the benefit in corrosion control that is provided by raising the pond solution pH to 9.2, whilst maintaining the boron level at 1250 gm -3 . The greater corrosion protection provided by pH9.2 solution compared to the pH7 borate solution is demonstrated by a series of tests with non-active laboratory sensitised brace samples exposed to solutions dosed with chloride or sulphate in order to promote localised corrosion. The corrosion tests undertaken consisted of 5000 hour immersions at 32 0 C and shorter term electrochemically monitored experiments (rest potential, impedance, anodic current) generally conducted at 22 0 C. The pH9.2 solution effectively inhibited the initiation of crevice and intergranular corrosion in the presence of low levels of chloride and sulphate, whereas the pH7 solution did not always do so. However, the pH9.2 solution, dosed with 40 gm -3 chloride, failed to suppress fully crevice corrosion initiated in unborated 40 gm -3 chloride solution at 22 0 C. Fluoride is not deleterious at low levels ∼ 10 gm -3 in the borate solutions. The significant improvement in corrosion control demonstrated for the change from pH7 to pH9.2 borate solution on laboratory sensitised brace samples should ideally be confirmed using complete irradiated AGR fuel elements. (U.K.)

A History of Dosimetry for the Advanced Gas-cooled Reactors

Directory of Open Access Journals (Sweden)

Shaw Simon

2016-01-01

Full Text Available This paper presents a summary of the methods used in the first ∼40 years of AGR neutron dosimetry and nuclear heating calculations, and the influence of the earlier Magnox reactor dosimetry programme. While the current state-of-the-art Monte Carlo methods are extremely powerful they still require very careful consideration of the quality of the input data, nuclear data validation and variance reduction techniques; in particular, this paper examines the difficulties in assuring the adequate convergence of calculations when Monte Carlo acceleration is applied in the presence of significant streaming paths through attenuating or scattering media.

Conceptual design study for the enhanced gas cooled reactor (EGCR)

International Nuclear Information System (INIS)

Nakano, M.; Sadahiro, D.; Ozaki, H.; Bryant, S.D.; Cheyne, A.; Gilroy, J.E.; Hulme, G.; Lennox, T.A.; Sunderland, R.E.; Beaumont, H.M.; Kida, M.; Nomura, M.

2001-01-01

The preliminary concept of the carbon dioxide cooled fast reactor EGCR has been studied as a Generation IV system. EGCR with MOX fuel has a very good core performance, a breeding ratio over 1.2, a long operating cycle of 24 months, and a high burnup of 150 GWd/t. The plant system is based on the successful AGR experience but provides 3600 MWth. Enhanced passive safety features are provided and a debris tray included. Preliminary costing studies show that EGCR can be competitive to LWRs and can be constructed on a similar schedule. This EGCR concept also shows development potential. (author)

Obreros agrícolas migrantes en Sinaloa

OpenAIRE

Florencio Posadas Segura

2015-01-01

El objetivo de este artículo es demostrar la presencia significativa de los obreros agrícolas migrantes, algunas características que la explican y la pauperización que experimentan. La causa principal de la migración es la desocupación; los empresarios controlan los métodos de contratación, trasportación y explotación, y los jornaleros rurales migrantes trabajan más, ganan menos y su situación es mayormente miserable. Esto se ilustra con el caso de Villa Benito Juárez, Sinaloa, que prueba la ...

Metodología para evaluar el impacto de la maquinaria agrícola sobre los recursos naturales del medio ambiente

Directory of Open Access Journals (Sweden)

Norge Díaz Rodríguez

2007-01-01

Full Text Available Se realizó una propuesta de metodología para evaluar el impacto que ejerce la maquinaria agrícola sobre algunos de los recursos naturales del medio ambiente. Durante su explotación la maquinaria agrícola, como unidad energética para el trabajo agrícola, produce un conjunto de impactos negativos sobre el medio en tres direcciones fundamentales: suelo, aire, y agua. A pesar de existir conciencia sobre este problema, no se disponen de herramientas apropiadas para hacer una evaluación certera de la magnitud de estos impactos, lo cual no es una simple tarea.

Trabajadores agrícolas migrantes en Baja California. Vinculación con la migración internacional

Directory of Open Access Journals (Sweden)

Ma. Eugenia Anguiano Téllez

1989-09-01

Full Text Available En este ensayo los jornaleros agrícolas migrantes son clasificados en dos estratos: el primero, considera la migración internacional, es decir, aquéllos que se internan en Estados Unidos con el propósito de conseguir empleo; y el segundo, corresponde a la migración interna de los trabajadores agrícolas que permanecen en Baja California para laborar en los valles de Mexicali y San Quintín.En este trabajo se señalan las diferencias entre estos dos estratos, tanto de carácter económico como en los niveles de educación; asimismo, se comparan las características de los jornaleros agrícolas migrantes que cruzan a Estados Unidos por Mexicali y por Tijuana, según su actividad económica de procedencia y su expectativa de empleo en los Estados Unidos.

Solo agrícola e agricultura em espaço urbano: dinâmicas. O exemplo de Évora

Directory of Open Access Journals (Sweden)

Maria Freire

2014-12-01

Full Text Available O objetivo do artigo é melhorar o entendimento sobre o significado da componente agrícola em espaço urbano para as sociedades e perspetivar estratégias no sentido de promover o património solo agrícola e a permanência e sustentabilidade do uso agrícola em espaço urbano. A metodologia de trabalho seguida compreende a análise da dinâmica de evolução urbana, associada à presença da agricultura em espaço urbano em Évora, numa perspetiva que inclui o seu significado nos domínios históricos, sociais, económicos, ecológicos e estéticos.

El Banco Nacional de Fomento en el desarrollo del sector agrícola durante el quinquenio 1992-1996. Propuesta a mediano plazo.

OpenAIRE

Proaño Gaibor, Alfonso

1998-01-01

El estudio contiene un panorama de la economía y del sector agrícola nacional, las políticas económicas aplicadas en el período de estudio, sus indicadores macroeconómicos, el PIB, el tipo de cambio y la incidencia de la agricultura en la población económicamente activa. El sector agrícola es analizado desde la perspectiva del comercio exterior, evaluando importaciones y exportaciones del sector agrícola, resultados en balanza comercial y proyección en el mercado global. La agricultura en...

The identification of an homogenous critical group using statistical extreme-value theory: application to laverbread consumers and the Windscale effluent discharges

International Nuclear Information System (INIS)

Beach, S.

1974-04-01

The International Commission of Radiological Protection states that a critical group should be representative of those individuals in the population expected to receive the highest dose. The appropriate dose limit should then be applied to the mean dose of this group. The edible seaweed Porphyra (laverbread) has been identified as the link in the critical exposure pathway limiting discharges of controlled low-level radioactive liquid waste from Windscale. The frequency distributions of the largest values of samples of 10, 20, 30, 40 and 50 male and female, child and adult consumers of laverbread are determined from the parent distributions by Monte Carlo sampling methods. From these results the extreme-value distribution of adult males of samples of 30 is taken to be a good estimate of the critical group, from which the median consumption rate of laverbread consumed per day is 55 g. The annual collective organ dose delivered to the lower large intestine of the total laverbread consumer group is estimated to be 266 man-rem. (author)

Training simulator for advanced gas-cooled reactor (AGR) shutdown sequence equipment

International Nuclear Information System (INIS)

Shankland, J.P.; Nixon, G.L.

1978-01-01

Successful shutdown of nuclear plant is of prime importance for both safety and economic reasons and large sums of money are spent on equipment to make shutdowns fully automatic, thus removing the possibility of operator errors. While this aim can largely be realized, one must consider the possibility of automatic equipment or plant failures when operators are required to take manual action, and off-line training facilities should be available to operating staff to minimize the risk of incorrect actions being taken. This paper presents the practice adopted at Hunterston 'B' Nuclear Power Station to solve this problem and concerns the computer-based training simulator for the Reactor Shutdown Sequence Equipment (RSSE) which was commissioned in January 1977. The plant associated with shutdown is briefly described and the reasoning which shows the need for a simulator is outlined. The paper also gives details of the comprehensive facilities available on the simulator and goes on to describe the form that shutdown training takes and the experience gained at this time. (author)

Commissioning methods applied to the Hunterston 'B' AGR operator training simulator

International Nuclear Information System (INIS)

Hacking, D.

1985-01-01

The Hunterston 'B' full scope AGR Simulator, built for the South of Scotland Electricity Board by Marconi Instruments, encompasses all systems under direct and indirect control of the Hunterston central control room operators. The resulting breadth and depth of simulation together with the specification for the real time implementation of a large number of highly interactive detailed plant models leads to the classic problem of identifying acceptance and acceptability criteria. For example, whilst the ultimate criterion for acceptability must clearly be that within the context of the training requirement the simulator should be indistinguishable from the actual plant, far more measurable (i.e. less subjective) statements are required if a formal contractual acceptance condition is to be achieved. Within the framework, individual models and processes can have radically different acceptance requirements which therefore reflect on the commissioning approach applied. This paper discusses the application of a combination of quality assurance methods, design code results, plant data, theoretical analysis and operator 'feel' in the commissioning of the Hunterston 'B' AGR Operator Training Simulator. (author)

Existe convergência espacial da produtividade agrícola no Brasil?

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Eduardo Simões de Almeida

2008-03-01

Full Text Available Este trabalho analisa a convergência espacial da produtividade agrícola da terra para as microrregiões brasileiras entre o período de 1991 a 2003. Tal análise avalia se há evidências para a existência de convergência beta da produtividade agrícola, controlando-se explicitamente para efeitos espaciais. Para tanto, conduziu-se preliminarmente uma análise exploratória de dados espaciais, que detectou a presença de autocorrelação espacial para a produtividade da terra. Numa etapa posterior, desenvolveram-se modelos econométricos espaciais para a análise da convergência.This work analyzes the convergence of land productivity for Brazilian regions from 1991 to 2003. It evaluates if there is or not beta convergence of the agricultural productivity, controlling explicitly for spatial effects. To do so, an exploratory spatial data analysis was previously implemented and the presence of spatial autocorrelation for the land productivity was detected. In addition, spatial econometric models were developed for the convergence analysis.

Opposing Roles of the Staphylococcus aureus Virulence Regulators, Agr and Sar, in Triton X-100- and Penicillin-Induced Autolysis

OpenAIRE

Fujimoto, David F.; Bayles, Kenneth W.

1998-01-01

The regulation of murein hydrolases is a critical aspect of peptidoglycan growth and metabolism. In the present study, we demonstrate that mutations within the Staphylococcus aureus virulence factor regulatory genes, agr and sar, affect autolysis, resulting in decreased and increased autolysis rates, respectively. Zymographic analyses of these mutant strains suggest that agr and sar exert their effects on autolysis, in part, by modulating murein hydrolase expression and/or activity.

An investigation into the use of a fast breeder reactor to incinerate actinide waste from the U.K. nuclear power programme

International Nuclear Information System (INIS)

Harte, G.A.; Clarke, R.H.

1976-12-01

Preliminary investigations are described into the effect of actinide removal and incineration (i.e. re-irradiation in a high neutron flux) on the long term hazards of reprocessing wastes from a Magnox reactor and from a notional CFR operated on plutonium from a Magnox reactor and also from an AGR. The actinides neptunium, americium and curium extracted from these wastes would be amenable to incineration in a fast breeder reactor core with fluxes of the order of 10 16 ncm -2 s -1 . An incineration period of 35 years was found to achieve a reduction in hazard, for most cooling periods up to one million years. The reductions were 2 to 3 orders of magnitude for the Magnox wastes and 4 orders of magnitude for the waste from CFR fuelled with AGR-plutonium. The large reduction factors do not apply to the hazards of reprocessing wastes as a whole, however, since one actinide separation has been achieved the residual quantities of uranium and plutonium in the waste stream, assumed here to be 0.1% of the original fuel inventory of these elements, become dominant in determining the hazard. Shorter incineration periods may serve to reduce the hazards of the extracted transuranics below the levels determined by these residues. A discussion of the hazards associated with reprocessing wastes as compared to those associated with uranium mill tailings attempts to place the nuclear waste disposal problem in perspective. (author)

Project WAGR: The UK demonstration project for power reactor decommissioning - removing the core and looking to completion

International Nuclear Information System (INIS)

Benest, T. G.

2003-01-01

The United Kingdom Atomic Energy Authority (UKAEA) has built and operated a wide range of nuclear facilities since the late 1940's. UKAEA's present mission is to restore the environment of these facilities in a safe and environmentally responsible manner. This restoration includes the decommissioning of a number of redundant research and power reactors, one of which is the Windscale Advanced Gas-cooled Reactor (WAGR). Following shut down, UKAEA decided to continue the prototype function of the reactor into the decommissioning phase to develop dismantling techniques and establish waste routes. The reactor core and pressure vessel are now being dismantled in a programme of 10 campaigns, seven of which have been completed since 1998. It is anticipated that the current programme will be completed by summer 2005. This paper outlines the history of the reactor, the operation of the waste-processing route, the installed dismantling equipment and the successful completion of the first seven campaigns. This earlier work has been described in a number of publications and conferences, so this paper concentrates on recent work to select and develop cutting equipment to dismantle the core support structures and the pressure vessel. The decommissioning of the Windscale Advance Gas-cooled reactor is being undertaken to demonstrate that a power reactor can be decommissioned shortly after shutdown. The removal of the core and pressure vessel has been broken down into a series of 10 campaigns associated with particular core components. The first 7 campaigns have been successfully completed and the 8., is expected to commence in September 2003 17 months earlier than planned. Dismantling methodologies and tools have been developed specifically for each of these campaigns. Full-scale mock-ups have been used to test the tools, train the operators and assess the duration of operations. However, despite successful trials, operational experience has shown that some of these tools have not

A summary of the results from the DOE advanced gas reactor (AGR) fuel development and qualification program

Energy Technology Data Exchange (ETDEWEB)

Petti, David Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2017-04-01

Modular high temperature gas-cooled reactor (HTGR) designs were developed to provide natural safety, which prevents core damage under all licensing basis events. The principle that guides their design concepts is to passively maintain core temperatures below fission product release thresholds under all accident scenarios. The required level of fuel performance and fission product retention reduces the radioactive source term by many orders of magnitude relative to source terms for other reactor types and allows a graded approach to emergency planning and the potential elimination of the need for evacuation and sheltering beyond a small exclusion area. Achieving this level, however, is predicated on exceptionally high coated-particle fuel fabrication quality and excellent performance under normal operation and accident conditions. The design goal of modular HTGRs is to meet the Environmental Protection Agency (EPA) Protective Action Guides (PAGs) for offsite dose at the Exclusion Area Boundary (EAB). To achieve this, the reactor design concepts require a level of fuel integrity that is far better than that achieved for all prior U.S.-manufactured tristructural isotropic (TRISO) coated particle fuel.

Metodologías para establecer valores de referencia de metales pesados en suelos agrícolas: Perspectivas para Colombia

Directory of Open Access Journals (Sweden)

Rueda Saa Germán

2011-09-01

Full Text Available

Los problemas ambientales de los metales pesados en los suelos están relacionados con su carácter tóxico cuando se acumulan o cuando interactüan con algunas propiedades especificas, se movilizan a  través del perfil a la cadena trófica mediante los cuerpos de agua o los cultivos y pueden llegar a afectar la salud humana. En países desarrollados el establecimiento de valores de referencia de estos metales ha permitido el mejoramiento de la planeación y la gestión ambiental del recurso suelo, y se ha convertido en un instrumento de control para las entidades ambientales que ha permitido evaluar el impacto en diferentes actividades agrícolas.

En este artículo se analizan diferentes conceptos relacionados con los niveles de metales pesados en suelos agrícolas y la incidencia de las características edafológicas en su concentración. Se revisan, igualmente, algunas metodologias para derivar valores de referencia especificos aplicables a suelos agrícolas colombianos, y se plantean algunas perspectivas orientadas a la protección y recuperación de suelos en el país. En Colombia en la actualidad no se cuenta con criterios y estándares de calidad para metales pesados en suelos agrícolas; por esto se hace necesario gestionar el apoyo de entidades gubernamentales con el fin de iniciar y desarrollar investigaciones en diferentes sectores agricolas primarios, contribuyendo de esta forma a garantizar la producción agrícola y la sostenibilidad ambiental del recurso suelo.

Considerations on the design of a helium circulator for a high temperature modular reactor system

International Nuclear Information System (INIS)

Dumm, K.; Donaldson, J.

1988-01-01

A modular helium cooled, high temperature reactor system with a thermal output of 200 MW per reactor has been developed by the KWU group for cogeneration of electricity and process steam. The flow of the reactor coolant - Helium at 60 bars and 250/700 deg. C is maintained by one circulator per reactor. The circulator is driven by a variable speed Siemens asynchronous motor and is submerged in the helium primary system. For operational reasons high reliability and availability of the circulator is required. The operational requirements for the circulator design are presented in this paper. The actual design has been carried out in close cooperation with the designer and manufacturer of all submerged circulators operating in AGR plants in Great Britain, James Howden Co. Renfrew, Scotland. Design solutions received so far and mainly based on sufficiently proven components - such as oil bath lubricated bearing systems - will be described. Special attention will be paid on the necessary test work; especially for the prototype to confirm the lay out. (author). 9 figs

Safety and dose management during decommissioning of a fire damaged nuclear reactor

International Nuclear Information System (INIS)

Pomfret, D.G.

2000-01-01

Windscale Piles 1 and 2 in Cumbria in the UK were constructed in the early 1950s. They were not intended to produce electricity but were for military purposes only. They were graphite-moderated, air-cooled reactors with horizontal fuel channels fuelled with uranium rods clad in finned aluminium. In October 1957, Windscale Pile 1 suffered a core fire during a planned release of Wigner energy and both Piles were subsequently closed down. Following the fire, Pile 2 was defuelled entirely and as much fuel as was possible was removed from Pile 1. However, it is estimated that up to 15 Te of fuel remains in the core, a large proportion of which is located in the central Fire Affected Zone (FAZ). The condition of the fuel and graphite moderator in the FAZ is not known. It is possible that the moderator could contain voidage, greatly reduced density graphite and fused materials in a disordered matrix. It is probable that there is residual Wigner energy in the graphite. Use of water as part of the attempt to extinguish the fire, together with the possibility that the solidification of molten materials or other local sealing mechanisms could have excluded air mean that uranium hydrides, carbides and other pyrophorics may be present within the core. Pile 1 is now being decommissioned and a considerable amount of preparatory work has already been carried out during Phase 1. Phase 2 decommissioning, which will remove the residual fuel, the moderator and associated steelwork, condition the wastes and place them in a purpose built store is now underway. This work will be carried out for the site licensee, the United Kingdom Energy Authority, by a consortium of British Nuclear Fuels plc, Rolls Royce and NUKEM. This paper will describe the methods to be used to decommission Pile 1 and the systems and procedures which will be used to ensure that it is done safely and with the lowest reasonably practicable environmental impact. It will also describe the methods which will be used to

Estudio de los métodos para la evaluación de los proveedores para una empresa de fabricación de maquinaria agrícola

OpenAIRE

Vilalta Martí, Josep M.

2012-01-01

El objeto de este proyecto es el estudio de los métodos para la evaluación de los proveedores para una empresa de fabricación de maquinaria agrícola y la implantación de la misma. Concretamente maquinaria agrícola pesada destinada al transporte de productos agrícolas. Dicha fábrica estará situada en la provincia de Lérida.

Nuclear decommissioning

International Nuclear Information System (INIS)

Lawton, H.

1987-01-01

Sufficient work has now been done, on a world-wide basis, to justify confidence that full decommissioning of nuclear installations, both plant and reactors, can be carried out safely and efficiently. Projects in several countries should confirm this in the next few years. In the United Kingdom, good progress has been made with the Windscale Advanced Gas-cooled Reactor and supporting development work is finding solutions to resolve uncertainties. Estimates from several sources suggest that decommissioning costs can be kept to an acceptable level. (author)

Necesidades educacionales sobre riesgo de plaguicidas en el contexto socio-ambiental de las comunidades agrícolas de Sonora

Directory of Open Access Journals (Sweden)

M.I. Silveira Gramont

2016-01-01

Full Text Available Para proponer estrategias de educación y comunicación sobre plaguicidas en las comunidades agrícolas de Sonora, se requiere situar la problemática de la exposición a plaguicidas en el contexto socio-cultural y ambiental de las comunidades afectadas, tomando en cuenta los factores que contribuyen al mayor riesgo de exposición de los trabajadores agrícolas y de sus familias. Este estudio examina los factores poblacionales, educacionales, culturales y de trabajo de habitantes y trabajadores agrícolas de dichas comunidades, así como las limitaciones de infraestructura comunitaria y de condiciones de vivienda en relación al riesgo de contaminación por plaguicidas. Sobre la base de este análisis se proponen posibles alternativas educacionales orientadas a mitigar tal riesgo en el contexto socio-cultural de dichas comunidades. Método De los estudios reportados sobre la presencia de residuos de plaguicidas en productos agrícolas y acuícolas, en suelos, agua, medio ambiente y en líquidos corporales de niños y adultos de Sonora, se puede concluir que tanto los trabajadores agrícolas como la población que reside cerca de las zonas agrícolas, están sujetos a un mayor riesgo de contaminación por plaguicidas. Para la realización del presente estudio se seleccionaron cinco comunidades localizadas en los valles agrícolas más productivos de Sonora, en las cuales se han llevado a cabo investigaciones relacionadas con plaguicidas. Básicamente, se analizó la información obtenida de encuestas aplicadas a residentes y trabajadores agrícolas de dichas comunidades, para explorar su conocimiento sobre uso y manejo de plaguicidas, percepción del riesgo que tales sustancias representan y las prácticas de protección personal que llevan a cabo para la prevención de dichos riesgos (en el hogar y trabajo. También se describe la infraestructura de los poblados y las viviendas de sus habitantes en relación al potencial de riesgo de contaminaci

Planificación estratégica de un sistema provincial de extensión agrícola (Sipea) para la Provincia de Acobamba

OpenAIRE

Yzarra Aguilar, Adelfa

2017-01-01

El objetivo fue analizar la realidad actual del servicio de extensión agrícola en la provincia de Acobamba, región Huancavelica, para proponer uno que articule los componentes hacia una óptima calidad del servicio, realizando los análisis de carácter externo positivo o negativo que favorece o perjudica el desarrollo del servicio de extensión agrícola. Se diseñó un plan estratégico para el sistema provincial de extensión agrícola para Acobamba, el enlace de los objetivos con la realidad actual...

Nuclear decommissioning

International Nuclear Information System (INIS)

Anon.

1987-01-01

The paper on nuclear decommissioning was presented by Dr H. Lawton to a meeting of the British Nuclear Energy Society and Institution of Nuclear Engineers, 1986. The decommissioning work currently being undertaken on the Windscale advanced gas cooled reactor (WAGR) is briefly described, along with projects in other countries, development work associated with the WAGR operation and costs. (U.K.)

Sellafield

International Nuclear Information System (INIS)

1984-01-01

This small, illustrated, booklet describes Sellafield under the headings: introduction (historical and general); organisation (Windscale Works; Calder Works); Magnox reprocessing (using nuclear fuel in a reactor; transport of fuel; used fuel stored in ponds; decanning of Magnox fuel; separation process; highly-active storage tanks; vitrification); waste disposal; health and safety; Calder Hall; future developments; training young people; community relations. (U.K.)

The effect on design of ISI

International Nuclear Information System (INIS)

Hart, J.D.

The evolution of in-service inspection techniques from the Magnox reactors through the AGR constructions is described. The following aspects are mentioned: general principles; factors that have influenced the development of ISI; objectives of ISI; examples drawn from AGR experience; major design changes to accommodate ISI; PWR reactors; occupational safety. (U.K.)

IRPhE-DRAGON-DPR, OECD High Temperature Reactor Dragon Project, Primary Documents

International Nuclear Information System (INIS)

2004-01-01

Description: The DRAGON Reactor Experiment (DRE): The first demonstration High temperature gas reactor (HTGR) was built in the 1960's. Thirteen OECD countries began a project in 1959 to build an experimental reactor known as Dragon at Winfrith in the UK. The reactor - which operated successfully between 1966 and 1975 - had a thermal output of 20 MW and achieved a gas outlet temperature of 750 deg. C. The High Temperature Reactor concept, if it justified its expectations, was seen as having its place as an advanced thermal reactor between the current thermal reactor types such as the PWR, BWR, and AGR and the sodium cooled fast breeder reactor. It was expected that the HTR would offer better thermal efficiency, better uranium utilisation, either with low enriched uranium fuel or high enriched uranium thorium fuel, better inherent safety and lower unit power costs. In the event all these potential advantages were demonstrated to be in principle achievable. This view is still shared today. In fact Very High Temperature Reactors is one of the concepts retained for Generation IV. Projects on constructing Modular Pebble Bed Reactors are under way. Here all available Dragon Project Reports (DPR) - approximately 1000 - are collected in electronic form. An index points to the reports (PDF format); each table in the report is accessible in EXCEL format with the aim of facilitating access to the data. These reports describe the design, experiments and modelling carried out over a period of 17 years. 2 - Related or auxiliary information: IRPHE-HTR-ARCH-01, Archive of HTR Primary Documents NEA-1728/01. 3 - Software requirements: Acrobat Reader, Microsoft Word, HTML Browser required

Metodologías para establecer valores de referencia de metales pesados en suelos agrícolas: perspectivas para Colombia

Directory of Open Access Journals (Sweden)

Germán Rueda Saa

2011-07-01

Full Text Available Los impactos ambientales de los metales pesados en los suelos están relacionados con su carácter tóxico cuando se acumulan o interactúan con algunas propiedades específicas, se movilizan a través del perfil a la cadena trófica mediante los cuerpos de agua o los cultivos y pueden llegar a afectar la salud humana. En países desarrollados el establecimiento de valores de referencia de estos metales ha permitido el mejoramiento de la planeación y la gestión ambiental del recurso suelo, y se ha convertido en un instrumento de control para las entidades ambientales que ha permitido evaluar el impacto en diferentes actividades agrícolas. En este artículo se analizan diversos conceptos relacionados con los niveles de metales pesados en suelos agrícolas y la incidencia de las características edafológicas en su concentración. Se revisan, igualmente, algunas metodologías para derivar valores de referencia específicos aplicables a suelos agrícolas colombianos, y se plantean algunas perspectivas orientadas a la protección y recuperación de suelos en el país. En Colombia en la actualidad no se cuenta con criterios y estándares de calidad para medir la contaminación por metales pesados en suelos agrícolas; por esto se hace necesario gestionar el apoyo de entidades gubernamentales con el fin de iniciar y desarrollar investigaciones en diferentes sectores agrícolas primarios, contribuyendo de esta forma a garantizar una producción más limpia y la sostenibilidad ambiental del recurso suelo.

An agr-like two-component regulatory system in Lactobacillus plantarum is involved in production of a novel cyclic peptide and regulation of adherence

NARCIS (Netherlands)

Sturme, M.H.J.; Nakayama, J.; Molenaar, D.; Murakami, Y.; Kunugi, R.; Fujii, T.; Vaughan, E.E.; Kleerebezem, M.; Vos, de W.M.

2005-01-01

We have analyzed a locus on the annotated Lactobacillus plantarum WCFS1 genome that showed homology to the staphylococcal agr quorum-sensing system and designated it lam for Lactobacillus agr-like module. Production of the lamBDCA transcript was shown to be growth phase dependent. Analysis of a

Results from the DOE Advanced Gas Reactor Fuel Development and Qualification Program

Energy Technology Data Exchange (ETDEWEB)

David Petti

2014-06-01

Modular HTGR designs were developed to provide natural safety, which prevents core damage under all design basis accidents and presently envisioned severe accidents. The principle that guides their design concepts is to passively maintain core temperatures below fission product release thresholds under all accident scenarios. This level of fuel performance and fission product retention reduces the radioactive source term by many orders of magnitude and allows potential elimination of the need for evacuation and sheltering beyond a small exclusion area. This level, however, is predicated on exceptionally high fuel fabrication quality and performance under normal operation and accident conditions. Germany produced and demonstrated high quality fuel for their pebble bed HTGRs in the 1980s, but no U.S. manufactured fuel had exhibited equivalent performance prior to the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. The design goal of the modular HTGRs is to allow elimination of an exclusion zone and an emergency planning zone outside the plant boundary fence, typically interpreted as being about 400 meters from the reactor. To achieve this, the reactor design concepts require a level of fuel integrity that is better than that claimed for all prior US manufactured TRISO fuel, by a few orders of magnitude. The improved performance level is about a factor of three better than qualified for German TRISO fuel in the 1980’s. At the start of the AGR program, without a reactor design concept selected, the AGR fuel program selected to qualify fuel to an operating envelope that would bound both pebble bed and prismatic options. This resulted in needing a fuel form that could survive at peak fuel temperatures of 1250°C on a time-averaged basis and high burnups in the range of 150 to 200 GWd/MTHM (metric tons of heavy metal) or 16.4 to 21.8% fissions per initial metal atom (FIMA). Although Germany has demonstrated excellent performance of TRISO-coated UO

Eficiência energética de um trator agrícola utilizando duas configurações de tomada de potência

Directory of Open Access Journals (Sweden)

Ulisses Giacomini Frantz

2014-07-01

Full Text Available A tomada de potência (TDP de um trator agrícola tem por principal finalidade transmitir a potência gerada no motor, para acionamento de órgãos ativos das máquinas agrícolas. Tendo em vista a necessidade de se aumentar a eficiência energética na agricultura, alguns fabricantes disponibilizam para os agricultores uma configuração de TDP que proporciona o acionamento dessas máquinas a um regime de rotação menor do motor do trator. Assim, a rotação da TDP é mantida podendo-se obter uma redução do consumo de combustível. Este trabalho objetivou quantificar o consumo de combustível de um trator agrícola, operando com duas configurações de TDP (normal e econômica em duas áreas agrícolas de relevo distinto. Como resultado, evidencia-se que, com a utilização da TDP econômica, tanto o consumo horário quanto o consumo operacional de combustível, em ambas as áreas trabalhadas, foi menor quando comparado à TDP normal.

The Agr quorum-sensing system regulates fibronectin binding but not hemolysis in the absence of a functional electron transport chain.

Science.gov (United States)

Pader, Vera; James, Ellen H; Painter, Kimberley L; Wigneshweraraj, Sivaramesh; Edwards, Andrew M

2014-10-01

Staphylococcus aureus is responsible for numerous chronic and recurrent infections, which are frequently associated with the emergence of small-colony variants (SCVs) that lack a functional electron transport chain. SCVs exhibit enhanced expression of fibronectin-binding protein (FnBP) and greatly reduced hemolysin production, although the basis for this is unclear. One hypothesis is that these phenotypes are a consequence of the reduced Agr activity of SCVs, while an alternative is that the lack of a functional electron transport chain and the resulting reduction in ATP production are responsible. Disruption of the electron transport chain of S. aureus genetically (hemB and menD) or chemically, using 2-n-heptyl-4-hydroxyquinoline N-oxide (HQNO), inhibited both growth and Agr activity and conferred an SCV phenotype. Supplementation of the culture medium with synthetic autoinducing peptide (sAIP) significantly increased Agr expression in both hemB mutant strains and S. aureus grown with HQNO and significantly reduced staphylococcal adhesion to fibronectin. However, sAIP did not promote hemolysin expression in hemB mutant strains or S. aureus grown with HQNO. Therefore, while Agr regulates fibronectin binding in SCVs, it cannot promote hemolysin production in the absence of a functional electron transport chain. Copyright © 2014, American Society for Microbiology. All Rights Reserved.

The assessment of environmental consequences of nuclear reactor accidents

International Nuclear Information System (INIS)

Beattie, J.R.

1981-01-01

Thorough measures are taken throughout all stages of design, construction and operation of nuclear power reactors, and therefore no accident producing any significant environmental impact is likely to occur. Nevertheless as a precaution, such accidents have been the subject of intensive scientific predictive studies. After a historical review of theoretical papers on reactor accidents and their imagined environmental impacts and of those accidents that have indeed occurred, this paper gives an outline of fission products or other radioactive substances that may or may not be released by an accident, and of their possible effects after dispersion in the atmosphere. This general introduction is followed by sections describing what are sometimes called 'design basis accidents' for four of the main reactor types (magnox, AGR, PWR and CDFR), the precautions against these accidents and the probable degree of environmental impact likely. The paper concludes with a reference to those very low probability accidents which might have more serious environmental impacts, and proceeds from there to show that both the individual and community risks from such accidents are numerically moderate compared to other risks apparently accepted by society. A brief reflection on the relevance of numerical values and perceived risk concludes the paper. (author)

Entre a propriedade e o salário. Memórias dos trabalhos agrícolas em Alpiarça (anos 50/80)

OpenAIRE

Dulce Freire

2006-01-01

Até aos anos 60 do século XX, Portugal foi um país essencialmente agrícola e rural. O rápido êxodo rural facilitou o abandono ou a transformação da agricultura. Apresenta-se aqui uma reflexão sobre os actuais processos de rememoração das práticas agrícolas numa vila do Ribatejo (Portugal) e sobre a amnésia social verificada relativamente ao passado agrícola, que decorre das transformações ocorridas e dos valores sociais e culturais associados à reconstrução da identidade da vila de Alp...

Entre a propriedade e o salário. Memórias dos trabalhos agrícolas em Alpiarça (anos 50/80

Directory of Open Access Journals (Sweden)

Dulce Freire

2006-09-01

Full Text Available Até aos anos 60 do século XX, Portugal foi um país essencialmente agrícola e rural. O rápido êxodo rural facilitou o abandono ou a transformação da agricultura. Apresenta-se aqui uma reflexão sobre os actuais processos de rememoração das práticas agrícolas numa vila do Ribatejo (Portugal e sobre a amnésia social verificada relativamente ao passado agrícola, que decorre das transformações ocorridas e dos valores sociais e culturais associados à reconstrução da identidade da vila de Alpiarça.

Necesidades educacionales sobre riesgo de plaguicidas en el contexto socio-ambiental de las comunidades agrícolas de Sonora

OpenAIRE

Silveira Gramont, M.I.; Aldana Madrid, L.; Valenzuela Quintanar, A.I.; Ochoa Nogales, C.B.; Jasa-Silveira, G.; Camarena Gómez, Beatriz

2016-01-01

Resumen Introducción: Para proponer estrategias de educación y comunicación sobre plaguicidas en las comunidades agrícolas de Sonora, se requiere situar la problemática de la exposición a plaguicidas en el contexto socio-cultural y ambiental de las comunidades afectadas, tomando en cuenta los factores que contribuyen al mayor riesgo de exposición de los trabajadores agrícolas y de sus familias. Este estudio examina los factores poblacionales, educacionales, culturales y de trabajo de habita...

Annual report 1986-1987

International Nuclear Information System (INIS)

1987-01-01

The United Kingdom Atomic Energy Authority operates seen sites: the Harwell Laboratory, Nuclear Power Development Establishments at Risley, Dounreay, Springfields and Windscale, the Winfrith Atomic Establishment and the Culham Laboratory. These are supported by Central Services of finance, administration, safety, etc. 1986/87 was the UKAEA's first year of financial operation as a Trading Fund and the accounts are, therefore, an important part of this report. The General Report includes information on finance, members, organisation, staff and information services. The Technical Report covers the UKAEA's interests in advanced gas-cooled reactors, water cooled-reactors, fast reactors, safety, fusion, underlying research and industrial and environmental technology. (U.K.)

Qualidade do emprego e condições de vida dos empregados assalariados rurais agrícolas e não agrícolas das mesorregiões mais e menos modernizadas do Estado de Minas Gerais : um estudo entre os anos 2000 a 2010

OpenAIRE

Gandolfi, Maria Raquel Caixeta

2016-01-01

Este trabalho tem como objetivo contribuir com os estudos em torno da qualidade do emprego e condições de vida da força de trabalho residente no setor rural das Mesorregiões de Minas Gerais, especificamente, o empregado assalariado. O recorte compreende as Mesorregiões de Minas Gerais, separadas por mais e menos modernizadas nas culturas do café, cana-de-açúcar e milho, envolvendo os empregados e as famílias agrícolas. Considerando a queda dos empregos agrícolas ocorridos na dé...

Staphylococcus aureus but not Listeria monocytogenes adapt to triclosan and adaptation correlates with increased fabI expression and agr deficiency

DEFF Research Database (Denmark)

Nielsen, Lene Nørby; Larsen, Marianne Halberg; Skovgaard, Sissel

2013-01-01

was initially 4 mg/L and remained unaltered by the exposure. The adapted S. aureus isolates retained normal colony size but displayed increased expression of fabI encoding an essential enzyme in bacterial fatty acid synthesis. Also, they displayed decreased or no expression of the virulence associated agr......C of the agr quorum sensing system. While most adapted strains of USA300 carried mutations in fabI, none of the adapted strains of 8325-4 did. Conclusions. Adaptability to triclosan varies substantially between Gram positive human pathogens. S. aureus displayed an intrinsically lower MIC for triclosan compared...... to L. monocytogenes but was easily adapted leading to the same MIC as L. monocytogenes. Even though all adapted S. aureus strains over-expressed fabI and eliminated expression of the agr quorum sensing system, adaptation in USA300 involved fabI mutations whereas this was not the case for 8325-4. Thus...

Orientación Agrícola

Directory of Open Access Journals (Sweden)

Gutiérrez E. Jorge

1941-06-01

Full Text Available Ya estamos sintiendo los efectos de la Guerra Europea y pocos son los preparativos que tenemos para organizar nuestra defensa. Al referirme a preparativos, no tengo en cuenta 108 militares, sino aquellos de carácter agrícola, base de todas las actividades en el orden económico. Cierto que los poderes legislativo y ejecutivo se han preocupado del problema, pero a mi modo de ver, en proporciones muy reducidas por carencia de dinero. Suceden cosas muy curiosas; todos nuestros compatriotas experimentan complacencia cuando se proyecta incrementar la Industria Agropecuaria, nervio y vida de la riqueza pública; el mismo legislador se contagia del entusiasmo; pero cuando llega el momento de asegurar la obra, apropiando las partidas del caso en los presupuestos, las nobles intenciones se esfuman y así han pasado los años y con ellos la oportunidad de hacemos fuertes.

El desarrollo tecnológico y la evolución de la frontera agrícola en el período 1961-2009

OpenAIRE

Casal, Luciano Martín

2014-01-01

Se analizó la evolución de la frontera agrícola argentina y su relación con el cambio tecnológico sucedido para el período 1961-2009, en particular de los activos fijos tangibles como la maquinaria agrícola, además de los cambios en la función de producción. Se buscó verificar la existencia de una relación funcional importante de largo plazo entre el aumento del capital fijo tangible y los cambios en la función de producción, para explicar la evolución de la frontera agrícola. Si bien la fron...

A review of the United Kingdom fast reactor programme

International Nuclear Information System (INIS)

Bramman, J.I.; Hickey, H.B.; Whitlow, W.H.; Frew, J.D.; Gregory, C.V.

1990-01-01

Total energy consumption in the UK in 1989 was 340 million tonnes of coal or coal equivalent, made up as follows: coal 31%, petroleum 35%, natural gas 24%, nuclear electricity 8%, hydroelectricity 1% and imported electricity 1%. About half of the nuclear electricity generated came from 14 Advanced Gas-Cooled Reactors (AGRs) and about half from the 24 older gas-cooled Magnox reactors, one Steam-Generating Heavy-Water Reactor (SGHWR) and one fast reactor (the Prototype Fast Reactor, PFR, at Dounreay). The privatization of the Electricity Supply Industry (ESI) in the UK is proceeding. On 9 November 1989, however, it was announced by the Secretary of State for Energy that the privatization plan would be changed and that the CEGB's nuclear stations were to remain in state ownership, through the formation of an additional company, Nuclear Electric. At the same time, the Secretary of State for Scotland announced the formation of a similar state-owned company, Scottish Nuclear. Nuclear Electric was asked, in the interim, to examine priorities in the whole nuclear field with particular reference to the improvement of the economics and performance of existing reactors, to the development of the Sizewell and alternative reactors and to the development of longer-term options such as the fast reactor and fusion. Nuclear Electric has been asked to formulate its new policy by June 1990. The PFR programme will continue to be funded by the UK government until March 1994. AEA Technology is endeavouring to find alternative funding to maintain the operation of the PFR until at least the year 2000. The House of Commons Select Committee on Energy stated in its report that the fast reactor ''is a matter for the British Government to foster as a long-term option for the generation of electricity in this country'', and recommended that in the interim the Government reassesses its position on this new technology in the light of increasing concern about CO 2 emissions and the long

AGR-3/4 Irradiation Test Train Disassembly and Component Metrology First Look Report

Energy Technology Data Exchange (ETDEWEB)

Stempien, John Dennis [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rice, Francine Joyce [Idaho National Lab. (INL), Idaho Falls, ID (United States); Harp, Jason Michael [Idaho National Lab. (INL), Idaho Falls, ID (United States); Winston, Philip Lon [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-09-01

The AGR-3/4 experiment was designed to study fission product transport within graphitic matrix material and nuclear-grade graphite. To this end, this experiment consisted of 12 capsules, each fueled with 4 compacts containing UCO TRISO particles as driver fuel and 20 UCO designed-to-fail (DTF) fuel particles in each compact. The DTF fuel was fabricated with a thin pyrocarbon layer which was intended to fail during irradiation and provide a source of fission products. These fission products could then migrate through the compact and into the surrounding concentric rings of graphitic matrix material and/or nuclear graphite. Through post-irradiation examination (PIE) of the rings (including physical sampling and gamma scanning) fission product concentration profiles within the rings can be determined. These data can be used to elucidate fission product transport parameters (e.g. diffusion coefficients within the test materials) which will be used to inform and refine models of fission product transport. After irradiation in the Advanced Test Reactor (ATR) had been completed in April 2014, the AGR-3/4 experiment was shipped to the Hot Fuel Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) for inspection, disassembly, and metrology. The AGR-3/4 test train was received at MFC in two separate shipments between February and April 2015. Visual examinations of the test train exterior did not indicate dimensional distortion, and only two small discolored areas were observed at the bottom of Capsules 8 and 9. No corresponding discoloration was found on the inside of these capsules, however. Prior to disassembly, the two test train sections were subject to analysis via the Precision Gamma Scanner (PGS), which did not indicate that any gross fuel relocation had occurred. A series of specialized tools (including clamps, cutters, and drills) had been designed and fabricated in order to carry out test train disassembly and recovery of capsule components (graphite

AGR-3/4 Irradiation Test Train Disassembly and Component Metrology First Look Report

Energy Technology Data Exchange (ETDEWEB)

Stempien, John Dennis [Idaho National Lab. (INL), Idaho Falls, ID (United States); Rice, Francine Joyce [Idaho National Lab. (INL), Idaho Falls, ID (United States); Harp, Jason Michael [Idaho National Lab. (INL), Idaho Falls, ID (United States); Winston, Philip Lon [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-03-01

The AGR-3/4 experiment was designed to study fission product transport within graphitic matrix material and nuclear-grade graphite. To this end, this experiment consisted of 12 capsules, each fueled with 4 compacts containing UCO TRISO particles as driver fuel and 20 UCO designed-to-fail (DTF) fuel particles in each compact. The DTF fuel was fabricated with a thin pyrocarbon layer which was intended to fail during irradiation and provide a source of fission products. These fission products could then migrate through the compact and into the surrounding concentric rings of graphitic matrix material and/or nuclear graphite. Through post-irradiation examination (PIE) of the rings (including physical sampling and gamma scanning) fission product concentration profiles within the rings can be determined. These data can be used to elucidate fission product transport parameters (e.g. diffusion coefficients within the test materials) which will be used to inform and refine models of fission product transport. After irradiation in the Advanced Test Reactor (ATR) had been completed in April 2014, the AGR-3/4 experiment was shipped to the Hot Fuel Examination Facility (HFEF) at the Materials and Fuels Complex (MFC) for inspection, disassembly, and metrology. The AGR-3/4 test train was received at MFC in two separate shipments between February and April 2015. Visual examinations of the test train exterior did not indicate dimensional distortion, and only two small discolored areas were observed at the bottom of Capsules 8 and 9. No corresponding discoloration was found on the inside of these capsules, however. Prior to disassembly, the two test train sections were subject to analysis via the Precision Gamma Scanner (PGS), which did not indicate that any gross fuel relocation had occurred. A series of specialized tools (including clamps, cutters, and drills) had been designed and fabricated in order to carry out test train disassembly and recovery of capsule components (graphite

The curious accountancy of decommissioning

International Nuclear Information System (INIS)

Anon.

1990-01-01

Financial provision for the decommissioning and waste management of the United Kingdom Magnox and AGR reactor is discussed. In the last set of accounts prior to privatisation a decommissioning provision of Pound 8.34 bn was indicated whereas previous figures had only shown Pound 2.88. It is suggested that the increase was only achieved on paper, without real financial provision. Estimates of decommissioning costs for the Magnox stations have increased greatly. Cost estimates for AGR decommissioning have still to be released but it is expected that the post-privatisation owners of the nuclear power industry, Nuclear Electric, will have to find Pound 6-7 bn to dismantle its own reactors. Much of this it hopes to put off for over 100 years. The South of Scotland Electicity Board has made much more realistic provision for its own Magnox and two AGR stations. Reprocessing costs for AGR reactor fuel is uncertain and high reprocessing and decommissioning costs will mean increases in the price of nuclear electricity. (UK)

State, Bank and Agricultural Credit in Sinaloa and Sonora: The Banco de Sinaloa and Banco Agrícola Sonorense, 1933-1976 Estado, banca y crédito agrícola en Sinaloa y Sonora: El Banco de Sinaloa y el Banco Agrícola Sonorense, 1933-1976

Directory of Open Access Journals (Sweden)

Gustavo Aguilar Aguilar

2011-01-01

Full Text Available In the Northwest of México the increase in the agricultural productivity in the years between 1940 and 1970, was due to the expansion of the farming lands, the use of improved seeds and fertilizer, mechanization, the greater availability of credit, the irrigation system and road improvement. The important intervention from the Mexican state to implement policies of investment with the support of internationally development agencies, and grant credit facilities for the development of agriculture trough the creation of official agricultural banks and the facilities to the constitution of private commercial banks. After the disarticulation of the bank in México due to the revolution, is advanced with steady steps in restructuring the banking system with the creation of a new banking law, the foundation of Banco de México and the Comision Nacional Bancaria in 1924; Banco Nacional de Credito Agricola (1926, the Banco Nacional de Credito Ejidal (1935, Banco Nacional de Comercio Exterior (1937 and the Banco Nacional Agropecuario (1965, which gave financial support to small farmers and ejidatarios (members of a cooperative. The main farmers of Sinaloa and Sonora in collaboration with the federal government through the Comision Monetaria and the Banco de México founded the Banco de Sinaloa and Banco Agricola Sonorense in 1933. Explain the impact these financial institutions had in the agricultural credit of Sinaloa and Sonora will be the central objective of this work.En el Noroeste de México el incremento en la productividad agrícola entre los años de 1940 y 1970, fue debido a la expansión de las tierras de cultivo, el uso de fertilizantes y semillas mejoradas, la mecanización, la mayor disponibilidad de créditos, a los sistemas de irrigación y el mejoramiento de las carreteras. Así como la importante intervención del Estado mexicano al implementar políticas de inversión con el apoyo de agencias internacionales de desarrollo, y otorgar

Estructura económica nacional: breve análisis del sector agrícola ecuatoriano

Directory of Open Access Journals (Sweden)

Jorge González-Sarango

2015-12-01

Full Text Available La estructura económica del Ecuador se ha basado, tradicionalmente, en el sector agrícola, el cual enfrenta un panorama económico mundial desalentador. El actual, pero bajo, precio del petróleo, podría incentivar a los importadores de materias primas, pero a la vez complicaría la situación de los exportadores de productos agrícolas, especialmente en economías, como la ecuatoriana, que no cuentan con estrategias de mejora de los niveles de productividad ante el régimen de tipo de cambio flexible de las economías vecinas y de aquellas que demandan bienes nacionales, es decir, que no pueden devaluar la moneda, para compensar el impacto de las pérdidas en los términos de intercambio de la demanda, que genera el abaratamiento del petróleo. Por otra parte, la tasa de crecimiento de la economía ecuatoriana ha tenido que ser replanteada ante los cambios en el contexto mundial, lo cual puede significar, un retroceso en cuanto a la planeación estatal y la determinación del Presupuesto General del Estado para el 2016. En este escenario, el sector agrícola de Ecuador, se ve abocado a contribuir con un porcentaje –cada vez mayor– a la composición del Producto Interno Bruto, sin contar con incentivos ni mejoras dirigidas precisamente a impulsar este sector.

Maximum permissible dietary contamination after the accidental release of radioactive materials from a nuclear reactor

Energy Technology Data Exchange (ETDEWEB)

Pochin, E E; Rock Carling, Ernest; Court Brown, W M [Medical Research Council, Committee on Protection against Ionizing Radiations, London (United Kingdom); and others

1960-12-01

After the accident to No. 1 pile at Windscale on October 10, 1957 (Atomic Energy Office, 1957), the Atomic Energy Authority asked the Medical Research Council for advice on the maximum intake of certain radioactive isotopes that should be regarded as permissible, under emergency conditions, for members of the general population living in, or deriving food from, an area contaminated owing to an accident to a reactor. The Council's Committee on Protection against Ionizing Radiations, together with its Subcommittees on Internal and External Radiations, has considered this problem, and concludes that the intake of radioactive materials by ingestion of contaminated food would generally be the limiting source of hazard after any such accident. Intake by inhalation, or radiation from the exterior, would become of importance only in rather special circumstances. In the following report, therefore, the Committee proposes maximum permissible levels of dietary contamination for the relevant isotopes in the emergency conditions envisaged. In proposing these levels, the Protection Committee has used the fullest information available on the radiation doses that would be delivered to different body tissues and at different ages by the isotopes concerned, and on the ways in which these materials would enter the body.

Maximum permissible dietary contamination after the accidental release of radioactive materials from a nuclear reactor

International Nuclear Information System (INIS)

Pochin, E.E.; Rock Carling, Ernest; Court Brown, W.M.

1960-01-01

After the accident to No. 1 pile at Windscale on October 10, 1957 (Atomic Energy Office, 1957), the Atomic Energy Authority asked the Medical Research Council for advice on the maximum intake of certain radioactive isotopes that should be regarded as permissible, under emergency conditions, for members of the general population living in, or deriving food from, an area contaminated owing to an accident to a reactor. The Council's Committee on Protection against Ionizing Radiations, together with its Subcommittees on Internal and External Radiations, has considered this problem, and concludes that the intake of radioactive materials by ingestion of contaminated food would generally be the limiting source of hazard after any such accident. Intake by inhalation, or radiation from the exterior, would become of importance only in rather special circumstances. In the following report, therefore, the Committee proposes maximum permissible levels of dietary contamination for the relevant isotopes in the emergency conditions envisaged. In proposing these levels, the Protection Committee has used the fullest information available on the radiation doses that would be delivered to different body tissues and at different ages by the isotopes concerned, and on the ways in which these materials would enter the body

Planificación de Maquinaria Agrícola

Directory of Open Access Journals (Sweden)

Alvarez Cardona Alberto

1979-06-01

Full Text Available Se entiende por planificación agrícola el conjunto de técnicas que permiten ver con anticipación suficiente la cantidad de maquinaria, tanto fuentes de potencia como implementos que serán requeridos para realizar un trabajo específico en un tiempo determinado; ó la cantidad de trabajo específico que podrá realizar un equipo con características ya definidas a través de un tiempo determinado; se analizan también bajo este concepto de planificación aquellos sistemas que permiten evaluar, controlar y ajustar la planificación propuesta a las circunstancias reales una vez iniciada ésta.

UK experience of safety requirements for thermal reactor stations

International Nuclear Information System (INIS)

Matthews, R.R.; Dale, G.C.; Tweedy, J.N.

1977-01-01

The paper summarises the development of safety requirements since the first of the Generating Boards' Magnox reactors commenced operation in 1962 and includes A.G.R. safety together with the preparation of S.G.H.W.R. design safety criteria. It outlines the basic principles originally adopted and shows how safety assessment is a continuing process throughout the life of a reactor. Some description is given of the continuous effort over the years to obtain increased safety margins for existing and new reactors, taking into account the construction and operating experience, experimental information, and more sophisticated computer-aided design techniques which have become available. The main safeguards against risks arising from the Generating Boards' reactors are the achievement of high standards of design, construction and operation, in conjunction with comprehensive fault analyses to ensure that adequate protective equipment is provided. The most important analyses refer to faults which can lead to excessive fuel element temperatures arising from an increase in power or a reduction in cooling capacity. They include the possibility of unintended control rod withdrawal at power or at start-up, coolant flow failure, pressure circuit failure, loss of boiler feed water, and failure of electric power. The paper reviews the protective equipment, and the policy for reactor safety assessments which include application of maximum credible accident philosophy and later the limited use of reliability and probability methods. Some of the Generating Boards' reactors are now more than half way through their planned working lives and during this time safety protective equipment has occasionally been brought into operation, often for spurious reasons. The general performance, of safety equipment is reviewed particularly for incidents such as main turbo-alternator trip, circulator failure, fuel element failures and other similar events, and some problems which have given rise to

Nuclear power and the energy crisis. Politics and the atomic industry. [United Kingdom

Energy Technology Data Exchange (ETDEWEB)

Burn, D

1978-01-01

An analysis is presented of the politics and economics of the decisions made during the past decade on the development and supply of nuclear power. The subject is treated under the following headings: first competitive reactor - the light water reactor (the paradox of LWR development, competitiveness accepted, the rise of costs - extent and sources, safety of the LWR, peak and collapse 1974 to 76, the LWR outside the United States); AGR to SGHWR (the course of AGR development, sources of the AGR disaster, response to failure - two governments decide, single D and C company, LWR versus SGHWR).

Redescubriendo El suelo: Su importancia ecológica y agrícola

Directory of Open Access Journals (Sweden)

Noé Manuel Montaño

2016-10-01

Full Text Available Redescubriendo el suelo: su importancia ecológica y agrícola es un libro muy completo, actualizado y sin duda será de consulta obligada para quienes hacen investigación edafológica y como material elemental para los cursos de pre- y posgrado de suelo y materias afines, tanto en México como en América Latina.

PIE on Safety-Tested Loose Particles from Irradiated Compact 4-4-2

Energy Technology Data Exchange (ETDEWEB)

Hunn, John D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gerczak, Tyler J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Morris, Robert Noel [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Baldwin, Charles A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Montgomery, Fred C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2016-04-01

Post-irradiation examination (PIE) is being performed in support of tristructural isotropic (TRISO) coated particle fuel development and qualification for High Temperature Gas-cooled Reactors (HTGRs). This work is sponsored by the Department of Energy Office of Nuclear Energy (DOE-NE) through the Advanced Reactor Technologies (ART) Office under the Advanced Gas Reactor Fuel Development and Qualification (AGR) Program. The AGR-1 experiment was the first in a series of TRISO fuel irradiation tests initiated in 2006. The AGR-1 TRISO particles and fuel compacts were fabricated at Oak Ridge National Laboratory (ORNL) in 2006 using laboratory-scale equipment and irradiated for 3 years in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) to demonstrate and evaluate fuel performance under HTGR irradiation conditions. Post-irradiation examination was performed at INL and ORNL to study how the fuel behaved during irradiation, and to test fuel performance during exposure to elevated temperatures at or above temperatures that could occur during a depressurized conduction cooldown event. This report summarizes safety testing and post-safety testing PIE conducted at ORNL on loose particles extracted from irradiated AGR-1 Compact 4-4-2.

Canvi d'us d'una nau agrícola a restaurant vinícola : el celler dels Mora

OpenAIRE

Mora Aller, Elisa

2017-01-01

El present treball fi de carrera tracta sobre el canvi d’ús d’una nau agrícola a restaurant vinícola. La nau es troba situada a la capital del vi, Vilafranca del Penedès. Durant els darrers anys, hi ha hagut un creixement important pel que fa al turisme del vi, a la zona de l’Alt Penedès. L’edifici objecte d’estudi, va ser construït pel meu avi a l’any 1980. Antigament, s’utilitzava per a guardar el bestiar i les eines agrícoles. Actualment, no hi ha bestiar, només s’utilitza per a guardar...

Development and application of thermal cutting techniques during Phase 1 decommissioning of WAGR

International Nuclear Information System (INIS)

White, S.J.

1992-01-01

The Windscale Advanced Gas Cooled Reactor is the UK's lead Stage 3 Decommissioning Project. One of the main objectives of the project is to demonstrate that a nuclear reactor can be safely and effectively decommissioned to a greenfield site using existing technology. Techniques using thermal cutting processes are used widely in industry and have been successfully adapted and applied to the first phase of the dismantling project. Over 1000 operational cuts have been performed using plasma cutting technology. Oxypropane and thermic lancing technique have also been applied to the dismantling the Top Biological Shield and Top Dome of the reactor pressure vessel. This paper describes the development and application of these standard technologies to the task of decommissioning a nuclear reactor. (Author)

Planning and progress of the WAGR decommissioning project

International Nuclear Information System (INIS)

Boorman, T.

1988-01-01

In the United Kingdom, the earliest production reactors, which will be decommissioned first, are of the Magnox type. The Windscale Advanced Gas-cooled Reactor, is however, sufficiently similar to make it a suitable prototype decommissioning project. The planning and progress so far is described. Special decommissioning equipment, including a remote dismantling machine, has been developed and a waste packaging building built on site. Its function is to enable all intermediate-level and low-level radioactive waste removed from the reactor vault by remote equipment to be packaged remotely into suitable containers. The work done on the WAGR decommissioning has shown that the dismantling of a power-producing reactor is feasible and can be accomplished using existing engineering techniques. (U.K.)

Decommissioning of nuclear power stations

International Nuclear Information System (INIS)

Gregory, A.R.

1988-01-01

In the United Kingdom the Electricity Boards, the United Kingdom Atomic Energy Authority (UKAEA) and BNFL cooperate on all matters relating to the decommissioning of nuclear plant. The Central Electricity Generating Board's (CEGB) policy endorses the continuing need for nuclear power, the principle of reusing existing sites where possible and the building up of sufficient funds during the operating life of a nuclear power station to meet the cost of its complete clearance in the future. The safety of the plant is the responsibility of the licensee even in the decommissioning phase. The CEGB has carried out decommissioning studies on Magnox stations in general and Bradwell and Berkeley in particular. It has also been involved in the UKAEA Windscale AGR decommissioning programme. The options as to which stage to decommission to are considered. Methods, costs and waste management are also considered. (U.K.)

Chemical cleaning of AGR boilers

International Nuclear Information System (INIS)

Moore, S.V.; Moore, W.; Rantell, A.

1978-01-01

AGR boilers are likely to require post service chemical cleaning to remove accumulated oxides at intervals of 15 - 35 kh. The need to clean will be based on an assessment of such factors as the development of flow imbalances through parallel tubes induced by the formation of rough oxide surfaces, an increasing risk of localised corrosion as the growth of porous oxides proceeds and the risk of tube blockage caused by the exfoliation of steam-grown oxides. The study has shown what heterogeneous multilayer oxides possessing a range of physical and chemical properties form on the alloy steels. They include porous and compact magnetites, chromium spinels and sesquioxide. Ammoniated citric acid has been shown to remove deposited and water-grown magnetites from the carbon and alloy steels but will not necessarily remove the substituted spinels grown on the alloy steels or the potentially spalling steam-grown magnetite on the A1SI 316 superheater. Citric acid supplemented with the reducing agent glyoxal completely removes all oxides from the boiler except the protective inner spinel formed on the 316. Removal of the spinels and compact magnetites occurs more by undercutting and physical detachment than by the dissolution. (author)

AGR-1 Compact 4-1-1 Post-Irradiation Examination Results

Energy Technology Data Exchange (ETDEWEB)

Demkowicz, Paul Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States); Harp, Jason M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Winston, Philip L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ploger, Scott A. [Idaho National Lab. (INL), Idaho Falls, ID (United States); van Rooyen, Isabella J. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-02-01

Destructive post-irradiation examination was performed on AGR-1 fuel Compact 4-1-1, which was irradiated to a final compact-average burnup of 19.4% FIMA (fissions per initial metal atom) and a time-average, volume-average temperature of 1072°C. The analysis of this compact focused on characterizing the extent of fission product release from the particles and examining particles to determine the condition of the kernels and coating layers. The work included deconsolidation of the compact and leach-burn-leach analysis, visual inspection and gamma counting of individual particles, metallurgical preparation of selected particles, and examination of particle cross-sections with optical microscopy, electron microscopy, and elemental analysis. Deconsolidation-leach-burn-leach (DLBL) analysis revealed no particles with failed TRISO or failed SiC layers (as indicated by very low uranium inventory in all of the leach solutions). The total fractions of the predicted compact inventories of fission products Ce-144, Cs-134, Cs-137, and Sr-90 that were present in the compact outside of the SiC layers were <2×10^-6, based on DLBL data. The Ag-110m fraction in the compact outside the SiC layers was 3.3×10^-2, indicating appreciable release of silver through the intact coatings and subsequent retention in the OPyC layers or matrix. The Eu-154 fraction was 2.4×10^-4, which is equivalent to the inventory in one average particle, and indicates a small but measurable level of release from the intact coatings. Gamma counting of 61 individual particles indicated no particles with anomalously low fission product retention. The average ratio of measured inventory to calculated inventory was close to a value of 1.0 for several fission product isotopes (Ce-144, Cs-134, and Cs-137), indicating good retention and reasonably good agreement with the predicted inventories. Measured-to-calculated (M/C) activity ratios for fission products Eu-154, Eu-155, Ru-106, Sb

Periferias e reestruturação agrícola

OpenAIRE

Dentinho, Tomaz; Rodrigues, Orlando

2007-01-01

As regiões vocacionadas par a agricultura encontram-se muitas vezes na situação de perificidade, pois têm produções agrícolas com elevada produtividade e capazes de competir nos mercados externos à sua região mas, devido a falhas de mercado ao longo da cadeia de valor, muito do valor criado a nível a nível regional acaba por gerar rendimento fora da região. Por outro lado são estas mesmas regiões periféricas que sofrem de forma mais notória os impactos das alterações nos mercados dos produtos...

Analise da vulnerabilidade de um solo agrícola, irrigado com águas poluídas

Directory of Open Access Journals (Sweden)

Benjamim Carvalho Lima Junior

2014-08-01

Full Text Available O reúso planejado de água de qualidade inferior contribui para uma gestão melhor dos recursos hídricos, favorecendo a produção agrícola em locais onde este fator de produção é escasso. No semiárido brasileiro a utilização de água de qualidade inferior em sistemas produtivos irrigados é em muitas situações, a única maneira de garantir a produção agrícola. Este trabalho objetivou identificar os impactos salinos em um solo agrícola cultivado com bananicultura irrigada com águas poluídas. Foram avaliados os parâmetros hidrodinâmico do solo condutividade hidráulica (K0, e porosidade drenável (μ, e os parâmetros de classificação salina do solo (pHes, CEes e PST. Foram realizadas análises exploratórias através de métodos estatísticos descritiva dos parâmetros hidrodinâmicos e modelagem geoestatística dos parâmetros de classificação salina. Observou no estudo o solo da área experimental encontra-se degradado por processo de salinização e sodicidade, ação provocada principalmente pela irrigação com água de qualidade inferior e deficiência na drenagem natural do solo.

Metodologia para estimar o número de dias trabalháveis com máquinas agrícolas

OpenAIRE

Estrada,Javier Solis; Schlosser,José Fernando; Farias,Marcelo Silveira de; Santos,Gustavo Oliveira do; Rüdell,Iury Yago Port

2015-01-01

No atual modelo de agricultura, é indispensável que o produtor conheça a real disponibilidade de tempo para a execução das operações agrícolas ao longo do ciclo das culturas. Este é o primeiro passo para se planejar e se obter maior eficiência na execução dessas operações, que estão sujeitas às variações do clima. As variáveis meteorológicas de uma determinada região influenciam diretamente no número de dias disponíveis para trabalhar com máquinas agrícolas. O objetivo deste trabalho foi esti...

Reestructuración agrícola de las familias productoras de maíz: estudio en San Mateo Ayecac, Tlaxcala, 2000-2008.

Directory of Open Access Journals (Sweden)

Ma. Concepción Alvarado Méndez

2011-01-01

Full Text Available La investigación tiene por objetivo analizar el mecanismo de transformación agrícola expresado en los cambios de la fuerza de trabajo agrícola en términos de su estructura económica así como las principales consecuencias económicas en la comunidad de San Mateo Ayecac, municipio de Tepetitla en el estado de Tlaxcala. Los resultados muestran una transformación de las familias productoras de granos básicos, expresados en el proceso productivo, específicamente en la disminución de labores, fertilización, disminución del trabajo familiar y en el rendimiento. A pesar de ello no existe abandono de la actividad agrícola y sigue siendo la base de la alimentación familiar y un importante abastecedor de alimentos de los mercados locales.

Cambio climático, ensalitramiento de suelos y producción agrícola en áreas de riego

Directory of Open Access Journals (Sweden)

Leonardo Pulido Madrigal

2016-04-01

Full Text Available Se analizó el impacto del clima en los problemas de salinidad, drenaje y producción agrícola en el Distrito de Riego 038 río Mayo Sonora el cual presenta afectaciones por sales en 32% de su superficie. Con datos de clima y agronómicos generados entre 1970-2001, se elaboraron modelos de regresión lineal simple para estudiar la relación entre la superficie ensalitrada con la temperatura ambiente, superficie afectada por niveles freáticos superficiales, volumen de riego, salinidad del agua de riego, precipitación pluvial, producción agrícola y productividad del agua. Asimismo, se correlacionó el manto freático con la temperatura, volumen de riego y precipitación pluvial. La producción se correlacionó con la salinidad del suelo, temperatura ambiente, superficie afectada por niveles freáticos superficiales y volumen de riego. Además, por medio de modelos de regresión lineal múltiple se determinaron las relaciones tanto de la superficie ensalitrada como de la producción agrícola, con la temperatura, superficie afectada por niveles freáticos superficiales, volumen de riego, superficie cosechada y precipitación pluvial. Los resultados evidenciaron que el aumento de superficie ensalitrada está relacionado con el incremento de temperatura; mismo que se asoció con la disminución del volumen de cosechas y con el aumento de superficie con niveles freáticos. Se encontró que los volúmenes de riego impactan en el incremento de la superficie agrícola con niveles freáticos someros y con el aumento de superficie ensalitrada. Con el calentamiento global los problemas de salinidad del suelo se incrementaron entre 24.1 y 15.8% en los estratos de suelo a 30 y 60 cm de profundidad, respectivamente. Asimismo, se estimó un crecimiento del 21.9% de superficies con niveles freáticos superficiales. El impacto del calentamiento global en el volumen de producción agrícola se estimó en una reducción del 18.9% del volumen de cosechas.

IUE observations of the hot components in two symbiotic stars. [R Agr and RW Hya, 1200 to 3200 A

Energy Technology Data Exchange (ETDEWEB)

Michalitsianos, A G [National Aeronautics and Space Administration, Greenbelt, MD (USA). Goddard Space Flight Center; Kafatos, M; Hobbs, R W; Maran, S P

1980-03-13

Ultraviolet measurements in the 1,200 - 3,200 A range are reported on two symbiotic stars, R Agr and RW Hya. The results indicate the presence of a hot component in each star, supporting the view that each is a binary system with a luminous red primary and a hot, sub-luminous companion. In the case of RW Hya the hot companion manifests itself by exciting a compact nebulosity while in the case of R Agr it is believed that the continuous spectrum of the hot star is directly detected, while the continuum of nebulosity excited by the hot star is detected at longer wavelengths.

Genetic algorithms and artificial neural networks for loading pattern optimisation of advanced gas-cooled reactors

Energy Technology Data Exchange (ETDEWEB)

Ziver, A.K. E-mail: a.k.ziver@imperial.ac.uk; Pain, C.C; Carter, J.N.; Oliveira, C.R.E. de; Goddard, A.J.H.; Overton, R.S

2004-03-01

A non-generational genetic algorithm (GA) has been developed for fuel management optimisation of Advanced Gas-Cooled Reactors, which are operated by British Energy and produce around 20% of the UK's electricity requirements. An evolutionary search is coded using the genetic operators; namely selection by tournament, two-point crossover, mutation and random assessment of population for multi-cycle loading pattern (LP) optimisation. A detailed description of the chromosomes in the genetic algorithm coded is presented. Artificial Neural Networks (ANNs) have been constructed and trained to accelerate the GA-based search during the optimisation process. The whole package, called GAOPT, is linked to the reactor analysis code PANTHER, which performs fresh fuel loading, burn-up and power shaping calculations for each reactor cycle by imposing station-specific safety and operational constraints. GAOPT has been verified by performing a number of tests, which are applied to the Hinkley Point B and Hartlepool reactors. The test results giving loading pattern (LP) scenarios obtained from single and multi-cycle optimisation calculations applied to realistic reactor states of the Hartlepool and Hinkley Point B reactors are discussed. The results have shown that the GA/ANN algorithms developed can help the fuel engineer to optimise loading patterns in an efficient and more profitable way than currently available for multi-cycle refuelling of AGRs. Research leading to parallel GAs applied to LP optimisation are outlined, which can be adapted to present day LWR fuel management problems.

Reproducción de Eisenia foetida en suelos agrícolas de áreas mineras contaminadas por cobre y arsênico.

OpenAIRE

ÁVILA, G.; GAETE, H.; MORALES, M.; NEAMAN, A.

2008-01-01

El objetivo del trabajo fue evaluar la toxicidad del cobre y arsénico en suelos agrícolas, mediante bioensayos estandarizados de toxicidad aguda y crónica sobre Eisenia foetida y relacionar la respuesta de ésta con las concentraciones de cobre y arsénico en los suelos. Los suelos agrícolas fueram muestreados en las inmediaciones de áreas mineras en la cuenca del río Aconcagua, Chile. E. foetida expuesta a los suelos estudiados mostró una baja mortalidad, indicando la ausencia de toxicidad agu...

Políticas trabalhista, fundiária e de crédito agrícola no Brasil

Directory of Open Access Journals (Sweden)

Gervásio Castro de Rezende

2006-03-01

Full Text Available Este artigo discute as causas do padrão concentrador do desenvolvimento agrícola brasileiro recente, expresso no predomínio da produção em grande escala, elevado índice de mecanização e baixa absorção de mão de obra não qualificada. Cita, inicialmente, a existência de duas posições antagônicas que procuram explicar esse fato: uma, que culpa a herança latifundiária de nossa agricultura, e a outra, que vê nisso um determinismo tecnológico, não havendo, assim, possibilidade de atuar sobre esse problema sem incorrer numa perda em termos de eficiência econômica. Este trabalho, contudo, atribui às políticas trabalhista agrícola, fundiária e de crédito agrícola, instituídas na década de 1960, a responsabilidade maior por esse problema. Conforme a análise apresentada, essas políticas inviabilizaram o mercado de trabalho agrícola temporário e a agricultura familiar, ao mesmo tempo em que fomentaram a mecanização agrícola e o predomínio da produção em grande escala. O trabalho termina propondo uma desregulamentação dos mercados de trabalho e de terra na agricultura brasileira, assim como uma redução drástica do subsídio ao crédito rural.This paper discusses the question of the concentrated pattern of agricultural development in Brazil, as expressed in the predominance of large-scale production, high level of mechanization and low absorption of non-qualified labor. It is proposed, initially, the existence of two conflicting explanations for this fact: the first, that blames our historical heritage, characterized by the predominance of the latifundio, and the second, that sees in this fact a technological determinism, with the implication that lesser concentration in agriculture would involve a loss of economic efficiency. This paper, however, attributes to the labor, land and credit policies directed to agriculture, instituted in the decade of 1960, the major responsibility for this problem. As the analysis

Nuclear fuel reprocessing in the UK

International Nuclear Information System (INIS)

Allardice, R.; Harris, D.; Mills, A.

1983-01-01

Nuclear fuel reprocessing has been carried out on an industrial scale in the United Kingdom since 1952. Two large reprocessing plants have been constructed and operated at Windscale, Cumbria and two smaller specialized plants have been constructed and operated at Dounreay, Northern Scotland. At the present time, the second of the two Windscale plants is operating, and Government permission has been given for a third reprocessing plant to be built on that site. At Dounreay, one of the plants is operating in its original form, whilst the second is now operating in a modified form, reprocessing fuel from the prototype fast reactor. This chapter describes the development of nuclear fuel reprocessing in the UK, commencing with the research carried out in Canada immediately after the Second World War. A general explanation of the techniques of nuclear fuel reprocessing and of the equipment used is given. This is followed by a detailed description of the plants and processes installed and operated in the UK

Nuclear fuel reprocessing in the UK

International Nuclear Information System (INIS)

Allardice, R.H.; Harris, D.W.; Mills, A.

1983-01-01

Nuclear fuel reprocessing has been carried out on an industrial scale in the United Kingdom since 1952. Two large reprocessing plants have been constructed and operated at Windscale, Cumbria and two smaller specialized plants have been constructed and operated at Dounreay, Northern Scotland. At the present time, the second of the two Windscale plants is operating, and Government permission has been given for a third reprocessing plant to be built on that site. At Dounreay, one of the plants is operating in its original form, whilst the second is now operating in a modified form, reprocessing fuel from the prototype fast reactor. This chapter describes the development of nuclear fuel reprocessing in the UK, commencing with the research carried out in Canada immediately after the Second World War. A general explanation of the techniques of nuclear fuel reprocessing and of the equipment used is given. This is followed by a detailed description of the plants and processes installed and operated in the UK. (author)

Ensino agrícola e influência norte-americana no Brasil (1945-1961

Directory of Open Access Journals (Sweden)

Sonia Regina de Mendonça

2010-12-01

Full Text Available O artigo trata das redefinições sofridas pelo Ensino Agrícola no Brasil, a partir da conjuntura marcada pelo fim da II Guerra Mundial/Guerra Fria, quando inúmeros acordos de "cooperação técnica" seriam firmados entre os governos brasileiro e estadunidense, objetivando "recuperar" seu novo público-alvo: o trabalhador rural adulto e analfabeto.

Return on experience on nuclear accidents

International Nuclear Information System (INIS)

Barre, Bertrand

2015-09-01

After a presentation of the International Nuclear and radiological Events Scale (INES scale), of its levels and criteria, this article proposes brief recalls of some nuclear accidents which occurred in nuclear reactors: Chalk River in Canada (1952), Windscale in England (1957), the universal Canadian reactor (NRU in 1958), the SL1 reactor of the Idaho National Laboratory in the USA (1961), the Swiss Lucens reactor (1969), Saint-Laurent des Eaux in France (1969 and 1980). More detailed descriptions are then given for the Three Mile Island accident in 1979, the Chernobyl accident in 1986, and the Fukushima accident in 2011. The main causes of these accidents are identified: loss of control of chain reaction, cooling defect on a stopped reactor, cooling defect on an operated reactor. Some lessons are drawn from these facts, and some characteristics of the EPR are outlined with respect with problems encountered in these accidents

A study on implementation of dynamic safety system in programmable logic controller for pressurized water reactor

International Nuclear Information System (INIS)

Kim, Ung Soo

1997-02-01

The dynamic safety system (DSS) is a computer based reactor protection system that has dynamic self-testing feature and fail-safe nature inherently. The inherent dynamic self-testing feature and fail-safe design provide a high level of reliability and low spurious trip rate. We can also reduce the time and human efforts to maintain the system by virtue of those features. Therefore, the application of the DSS to PWR has many advantages. The DSS has been applied only to advanced gas-cooled reactor (AGR) in the UK. In order to apply the DSS for PWR, the DSS has to be modified because there exist many differences between PWR and AGR for which the DSS was tested and installed. These differences are trip algorithms, monitored parameters, trip logics, and other conditions. In this study, the DSS algorithm is modified for PWR first. The modified DSS has several new features : 1) The modified DSS tests and processes time-dependent parameters, while the original DSS does not. 2) It has flexibility for handling several types of voting logic but the original DSS handles the only one type of voting - 2 out of 4 coincidence logic. Then, in this study, the modified DSS is implemented in programmable logic controller (PLC) using the ladder logic. Finally, the modified DSS is tested in two ways in this work : 1) The manual test is performed using direct input through the human computer interface (HCI) system. 2) The scenario based test is performed using input from the FISA-2/WS simulator. From the test results, it is shown that the modified DSS operates correctly in all conditions

Pioneiros da ecologia política agrária contemporânea The pioneers of the contemporary agrarian political ecology

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Humberto Miranda Nascimento

2009-12-01

Full Text Available O presente artigo tem por objetivo apresentar os pioneiros dos estudos materialistas sobre ecologia política agrária contemporânea. É feita uma análise das contribuições da Escola Russa de Estudos do Solo e de referências mais recentes aos escritos de Marx e Liebig. Nas considerações finais, enfatiza-se a necessidade de desenvolver a abordagem da Ecologia Política Agrária como maneira mais apropriada de entender a relação entre sistemas agrários, formações sociais e ecossistemas específicos em áreas rurais.The pioneering studies on the relationship between society and nature are important for the analysis of agricultural and ecological changes in rural areas. The goal of the present article is to introduce the contemporary pioneers of the agrarian ecology studies with a Marxist Materialism approach. The agrarian ecology describes the relations among agrarian systems, social formations and specific ecosystems in rural territories. Thence, the concept has a double function: turn the agrarian problem into an ecological theme and redefine its importance for the current studies on rural territory.

Single phase and two phase erosion corrosion in broilers of gas-cooled reactors

International Nuclear Information System (INIS)

Harrison, G.S.; Fountain, M.J.

1988-01-01

Erosion-corrosion is a phenomenon causing metal wastage in a variety of locations in water and water-steam circuits throughout the power generation industry. Erosion-corrosion can occur in a number of regions of the once-through boiler designs used in the later Magnox and AGR type of gas cooled nuclear reactor. This paper will consider two cases of erosion-corrosion damage (single and two phase) in once through boilers of gas cooled reactors and will describe the solutions that have been developed. The single phase problem is associated with erosion-corrosion damage of mild steel downstream of a boiler inlet flow control orifice. With metal loss rates of up to 1 mm/year at 150 deg. C and pH in the range 9.0-9.4 it was found that 5 μg/kg oxygen was sufficient to reduce erosion-corrosion rates to less than 0.02 mm/year. A combined oxygen-ammonia-hydrazine feedwater regime was developed and validated to eliminate oxygen carryover and hence give protection from stress corrosion in the austenitic section of the AGR once through boiler whilst still providing erosion-corrosion control. Two phase erosion-corrosion tube failures have occurred in the evaporator of the mild steel once through boilers of the later Magnox reactors operating at pressures in the range 35-40 bar. Rig studies have shown that amines dosed in the feedwater can provide a significant reduction in metal loss rates and a tube lifetime assessment technique has been developed to predict potential tube failure profiles in a fully operational boiler. The solutions identified for both problems have been successfully implemented and the experience obtained following implementation including any problems or other benefits arising from the introduction of the new regimes will be presented. Methods for monitoring and evaluating the efficiency of the solutions have been developed and the results from these exercises will also be discussed. Consideration will also be given to the similarities in the metal loss

Single phase and two phase erosion corrosion in broilers of gas-cooled reactors

Energy Technology Data Exchange (ETDEWEB)

Harrison, G S; Fountain, M J [Operational Engineering Division (Northern Area), Central Electricity Generating Board, Manchester (United Kingdom)

1988-07-01

Erosion-corrosion is a phenomenon causing metal wastage in a variety of locations in water and water-steam circuits throughout the power generation industry. Erosion-corrosion can occur in a number of regions of the once-through boiler designs used in the later Magnox and AGR type of gas cooled nuclear reactor. This paper will consider two cases of erosion-corrosion damage (single and two phase) in once through boilers of gas cooled reactors and will describe the solutions that have been developed. The single phase problem is associated with erosion-corrosion damage of mild steel downstream of a boiler inlet flow control orifice. With metal loss rates of up to 1 mm/year at 150 deg. C and pH in the range 9.0-9.4 it was found that 5 {mu}g/kg oxygen was sufficient to reduce erosion-corrosion rates to less than 0.02 mm/year. A combined oxygen-ammonia-hydrazine feedwater regime was developed and validated to eliminate oxygen carryover and hence give protection from stress corrosion in the austenitic section of the AGR once through boiler whilst still providing erosion-corrosion control. Two phase erosion-corrosion tube failures have occurred in the evaporator of the mild steel once through boilers of the later Magnox reactors operating at pressures in the range 35-40 bar. Rig studies have shown that amines dosed in the feedwater can provide a significant reduction in metal loss rates and a tube lifetime assessment technique has been developed to predict potential tube failure profiles in a fully operational boiler. The solutions identified for both problems have been successfully implemented and the experience obtained following implementation including any problems or other benefits arising from the introduction of the new regimes will be presented. Methods for monitoring and evaluating the efficiency of the solutions have been developed and the results from these exercises will also be discussed. Consideration will also be given to the similarities in the metal loss

PRAPRAG: software para planejamento racional de máquinas agrícolas PRAPRAG: software for rational planning of agricultural machines

OpenAIRE

Erivelto Mercante; Eduardo G. de Souza; Jerry A Johann; Antonio Gabriel Filho; Miguel A Uribe-Opazo

2010-01-01

O software PRAPRAG é uma ferramenta de escolha de máquinas e implementos agrícolas que apresentam o menor custo por área ou por quantidade produzida, bem como, faz o planejamento de aquisição das máquinas para a propriedade agrícola, do ponto de vista técnico e econômico. Foi utilizada a linguagem de programação Borland Delphi 3.0 e, a partir de prospectos das máquinas e implementos, criou-se um banco de dados onde o usuário pode cadastrar e modificar suas características de uso. O software m...

Analysis of Gln223Agr Polymorphism of Leptin Receptor Gene in Type II Diabetic Mellitus Subjects among Malaysians

Directory of Open Access Journals (Sweden)

Chong Pei Pei

2013-09-01

Full Text Available Leptin is known as the adipose peptide hormone. It plays an important role in the regulation of body fat and inhibits food intake by its action. Moreover, it is believed that leptin level deductions might be the cause of obesity and may play an important role in the development of Type 2 Diabetes Mellitus (T2DM, as well as in cardiovascular diseases (CVD. The Leptin Receptor (LEPR gene and its polymorphisms have not been extensively studied in relation to the T2DM and its complications in various populations. In this study, we have determined the association of Gln223Agr loci of LEPR gene in three ethnic groups of Malaysia, namely: Malays, Chinese and Indians. A total of 284 T2DM subjects and 281 healthy individuals were recruited based on International Diabetes Federation (IDF criteria. Genomic DNA was extracted from the buccal specimens of the subjects. The commercial polymerase chain reaction (PCR method was carried out by proper restriction enzyme MSP I to both amplify and digest the Gln223Agr polymorphism. The p-value among the three studied races was 0.057, 0.011 and 0.095, respectively. The values such as age, WHR, FPG, HbA1C, LDL, HDL, Chol and Family History were significantly different among the subjects with Gln223Agr polymorphism of LEPR (p < 0.05.

MicroRNA-1291 targets the FOXA2-AGR2 pathway to suppress pancreatic cancer cell proliferation and tumorigenesis

Science.gov (United States)

Qiu, Jing-Xin; Kim, Edward J.; Yu, Ai-Ming

2016-01-01

Pancreatic cancer is the fourth leading cause of cancer death in the United States. Better understanding of pancreatic cancer biology may help identify new oncotargets towards more effective therapies. This study investigated the mechanistic actions of microRNA-1291 (miR-1291) in the suppression of pancreatic tumorigenesis. Our data showed that miR-1291 was downregulated in a set of clinical pancreatic carcinoma specimens and human pancreatic cancer cell lines. Restoration of miR-1291 expression inhibited pancreatic cancer cell proliferation, which was associated with cell cycle arrest and enhanced apoptosis. Furthermore, miR-1291 sharply suppressed the tumorigenicity of PANC-1 cells in mouse models. A proteomic profiling study revealed 32 proteins altered over 2-fold in miR-1291-expressing PANC-1 cells that could be assembled into multiple critical pathways for cancer. Among them anterior gradient 2 (AGR2) was reduced to the greatest degree. Through computational and experimental studies we further identified that forkhead box protein A2 (FOXA2), a transcription factor governing AGR2 expression, was a direct target of miR-1291. These results connect miR-1291 to the FOXA2-AGR2 regulatory pathway in the suppression of pancreatic cancer cell proliferation and tumorigenesis, providing new insight into the development of miRNA-based therapy to combat pancreatic cancer. PMID:27322206

Analysis of Gln223Agr polymorphism of Leptin Receptor Gene in type II diabetic mellitus subjects among Malaysians.

Science.gov (United States)

Etemad, Ali; Ramachandran, Vasudevan; Pishva, Seyyed Reza; Heidari, Farzad; Aziz, Ahmad Fazli Abdul; Yusof, Ahmad Khairuddin Mohamed; Pei, Chong Pei; Ismail, Patimah

2013-09-18

Leptin is known as the adipose peptide hormone. It plays an important role in the regulation of body fat and inhibits food intake by its action. Moreover, it is believed that leptin level deductions might be the cause of obesity and may play an important role in the development of Type 2 Diabetes Mellitus (T2DM), as well as in cardiovascular diseases (CVD). The Leptin Receptor (LEPR) gene and its polymorphisms have not been extensively studied in relation to the T2DM and its complications in various populations. In this study, we have determined the association of Gln223Agr loci of LEPR gene in three ethnic groups of Malaysia, namely: Malays, Chinese and Indians. A total of 284 T2DM subjects and 281 healthy individuals were recruited based on International Diabetes Federation (IDF) criteria. Genomic DNA was extracted from the buccal specimens of the subjects. The commercial polymerase chain reaction (PCR) method was carried out by proper restriction enzyme MSP I to both amplify and digest the Gln223Agr polymorphism. The p-value among the three studied races was 0.057, 0.011 and 0.095, respectively. The values such as age, WHR, FPG, HbA1C, LDL, HDL, Chol and Family History were significantly different among the subjects with Gln223Agr polymorphism of LEPR (p < 0.05).

Status of national gas cooled reactor programmes

International Nuclear Information System (INIS)

1991-08-01

This report has been compiled as a central source of summary-level information on the present status of High Temperature Gas-Cooled Reactor (HTGR) programmes in the world and on future plans for the continued development and deployment of HTGRs. Most of the information concerns the programmes in the United States, Germany, Japan and the Soviet Union, countries that have had large programmes related to HTGR technology for several years. Summary-level information is also provided in the report on HTGR-related activities in several other countries who either have an increasing interest in the technology and/or who are performing some development efforts related to HTGR technology. The report contains a summary-level update on the MAGNOX and AGR programmes. This is the twelfth issue of the document, the first of which was issued in March, 1979. The report has been prepared in the IAEA Nuclear Power Technology Development Section. Figs and tabs

Migración internacional, actividades agrícolas y distribución del ingreso en una comunidad oaxaqueña, México

OpenAIRE

Renato Salas Alfaro

2012-01-01

Este trabajo explora el efecto que tiene la migración internacional y las remesas sobre las actividades agrícolas y la distribución del ingreso en una comunidad indígena que recientemente ha masificado su migración internacional. Se emplearon modelos para relacionar variables agrícolas contra factores productivos, socio demográficos y de financiamiento a la migración en el hogar, asimismo, la descomposición del coeficiente de Gini se utilizó para determinar el efecto que tienen las fuentes de...

Natural draught centralized dry store for irradiated fuel and active waste

International Nuclear Information System (INIS)

Bradley, N.; Brown, G.A.

1981-01-01

A modular design is described for the long term dry storage of irradiated fuel and vitrified fission products. The specification set by the Central Electricity Generating Board for the AGR fuel store was that the store should be capable of accommodating the lifetime discharge from 10 AGR reactors (7200 tonnes of irradiated fuel) and be cooled by natural convection. The fuel assemblies should be enclosed in individual steel containers. The store has an area for drying the AGR fuel and containering. The single dry cell storage capacities are, 5 years output from 1300 MWe station stored as fuel elements, or 14 year output from 1300 MWe thermal reactors stored as vitrified fission products. (U.K.)

Antropometria aplicada aos operadores de tratores agrícolas Anthropometrics applied to the agricultural tractors operators

Directory of Open Access Journals (Sweden)

José Fernando Schlosser

2002-12-01

Full Text Available O objetivo deste trabalho foi determinar o padrão antropométrico dos operadores de tratores agrícolas da Depressão Central do Rio Grande do Sul. Os operadores de tratores agrícolas foram medidos por meio de um painel constituído por duas chapas metálicas, permanecendo durante as medições em pé, eretos, com o mínimo de roupa possível e em contato com o painel. As variáveis medidas foram as seguintes: altura do corpo; altura ao nível dos olhos; altura ao nível dos olhos sentado; altura do cotovelo; alcance do braço; alcance da mão; distância pé-patela; apoio do assento. Os dados obtidos demonstram que há diferenças entre o biótipo do operador utilizado pela indústria de tratores agrícolas e o do operador da região, de forma que este último apresentou, para todas as medidas, à exceção do apoio do assento, uma média maior. Observa-se também que, para cada medida, os limites inferior e superior do intervalo onde se encontram 90% dos operadores avaliados foram, respectivamente, menores e maiores que o padrão utilizado pela indústria, caracterizando uma maior variação. Levando-se em consideração as diferenças existentes entre o perfil antropométrico dos operadores de tratores agrícolas da Depressão Central do Rio Grande do Sul e os parâmetros utilizados pela indústria, pode-se confirmar a hipótese de que os tratores agrícolas que se encontram atualmente em comercialização no Brasil podem não oferecer o conforto necessário ao operador desta região .The objective of this work was to evaluate the anthropometric measures of the agricultural tractor operators of the Central Region of Rio Grande do Sul State. The agricultural tractor operators were measured through a panel that was made of two metallic plates. During the measurement, they were standing, wearing the minimum amount clothes possible, and touching the panel. The measures body height, eyes level height (standing, eyes level height (sitting, elbow

Mecanización agrícola ¿Deterioro o conservación del suelo?

Directory of Open Access Journals (Sweden)

Armando Alvarado Chaves

2006-05-01

Full Text Available “Mecanización agrícola; ¿Deterioro o conservación del suelo?” trata sobre el mito de que la mecanización o preparación de los suelos, en forma mecánica, es el detonante del deterioro de los suelos por erosión sobre todo por erosión hídrica y en menor grado por erosión eólica. La erosión de los suelos puede ser de poca o de gran magnitud, dependiendo de cuatro factores, los cuales se analizan como errores que se cometen en el momento de preparar los suelos. Estos errores son, en realidad, los causantes del deterioro de los suelos por erosión y no la mecanización, ya que esta, bien planificada y aplicada, puede incluso servir para la conservaciónde los suelos y el medio ambiente. También se describen los implementos agrícolas que pueden usarse para reducir la erosión de los suelos, citando su forma de trabajo y algunas de las ventajas del uso de esos implementos.

Heysham II/Torness AGR steam generator

International Nuclear Information System (INIS)

Charcharos, A.N.; Wood, M.B.; Glasgow, J.R.

1988-01-01

The AGR Steam Generators for Heysham II and Torness Power Stations have been installed at site and are being operated in the initial low temperature commissioning plant engineering tests. In this paper a description of the high pressure once-through steam generators together with layout arrangements, materials employed, operating parameters, plant operating conditions and constraints is given. An outline of the development of the design through thermo-hydraulic considerations, mechanical design, instrumentation to component testing is presented. Special features of the design directed to accommodate such requirements as seismic loadings, waterside static and dynamic stability, gas flow induced vibration, thermal expansions are described in detail. The fabrication facilities employed and techniques selected and developed for the manufacture and assembly of the heating surfaces are presented. These include welding processes, tube manipulation and heat treatment with details of the automation applied to the processes. Operating experience in the early commissioning plant engineering tests at Site is described with an emphasis on those tests which provide the final confirmation of the design prior to operation at full load. The paper concludes with a description of the outstanding commissioning activities up to raise power. (author)

Heysham II/Torness AGR steam generator

Energy Technology Data Exchange (ETDEWEB)

Charcharos, A N [National Nuclear Corporation Ltd., Knutsford (United Kingdom); Wood, M B; Glasgow, J R [NEI Power Projects Ltd., Gateshead (United Kingdom)

1988-07-01

The AGR Steam Generators for Heysham II and Torness Power Stations have been installed at site and are being operated in the initial low temperature commissioning plant engineering tests. In this paper a description of the high pressure once-through steam generators together with layout arrangements, materials employed, operating parameters, plant operating conditions and constraints is given. An outline of the development of the design through thermo-hydraulic considerations, mechanical design, instrumentation to component testing is presented. Special features of the design directed to accommodate such requirements as seismic loadings, waterside static and dynamic stability, gas flow induced vibration, thermal expansions are described in detail. The fabrication facilities employed and techniques selected and developed for the manufacture and assembly of the heating surfaces are presented. These include welding processes, tube manipulation and heat treatment with details of the automation applied to the processes. Operating experience in the early commissioning plant engineering tests at Site is described with an emphasis on those tests which provide the final confirmation of the design prior to operation at full load. The paper concludes with a description of the outstanding commissioning activities up to raise power. (author)

Electron Microscopic Examination of Irradiated TRISO Coated Particles of Compact 6-3-2 of AGR-1 Experiment

Energy Technology Data Exchange (ETDEWEB)

Van Rooyen, Isabella Johanna [Idaho National Lab. (INL), Idaho Falls, ID (United States); Demkowicz, Paul Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States); Riesterer, Jessica Lori [Idaho National Lab. (INL), Idaho Falls, ID (United States); Miller, Brandon Douglas [Idaho National Lab. (INL), Idaho Falls, ID (United States); Janney, Dawn Elizabeth [Idaho National Lab. (INL), Idaho Falls, ID (United States); Harp, Jason Michael [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ploger, Scott Arden [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2012-12-01

The electron microscopic examination of selected irradiated TRISO coated particles of the AGR-1 experiment of fuel compact 6-3-2 are presented in this report. Compact 6-3-2 refers to the compact in Capsule 6 at level 3 of Stack 2. The fuel used in capsule 6 compacts, are called the “baseline” fuel as it is fabricated with refined coating process conditions used to fabricate historic German fuel, because of its excellent irradiation performance with UO2 kernels. The AGR-1 fuel is however made of low-enriched uranium oxycarbide (UCO). Kernel diameters are approximately 350 µm with a U-235 enrichment of approximately 19.7%. Compact 6-3-2 has been irradiated to 11.3% FIMA compact average burn-up with a time average, volume average temperature of 1070.2°C and with a compact average fast fluence of 2.38E21 n/cm

Sensitivity analysis of an Advanced Gas-cooled Reactor control rod model

International Nuclear Information System (INIS)

Scott, M.; Green, P.L.; O’Driscoll, D.; Worden, K.; Sims, N.D.

2016-01-01

Highlights: • A model was made of the AGR control rod mechanism. • The aim was to better understand the performance when shutting down the reactor. • The model showed good agreement with test data. • Sensitivity analysis was carried out. • The results demonstrated the robustness of the system. - Abstract: A model has been made of the primary shutdown system of an Advanced Gas-cooled Reactor nuclear power station. The aim of this paper is to explore the use of sensitivity analysis techniques on this model. The two motivations for performing sensitivity analysis are to quantify how much individual uncertain parameters are responsible for the model output uncertainty, and to make predictions about what could happen if one or several parameters were to change. Global sensitivity analysis techniques were used based on Gaussian process emulation; the software package GEM-SA was used to calculate the main effects, the main effect index and the total sensitivity index for each parameter and these were compared to local sensitivity analysis results. The results suggest that the system performance is resistant to adverse changes in several parameters at once.

The agr inhibitors solonamide B and analogues alter immune responses to Staphylococccus aureus but do not exhibit adverse effects on immune cell functions

DEFF Research Database (Denmark)

Baldry, Mara; Kitir, Betül; Frøkiær, Hanne

2016-01-01

Staphylococcus aureus infections are becoming increasingly difficult to treat due to antibiotic resistance with the community-associated methicillin-resistant S. aureus (CA-MRSA) strains such as USA300 being of particular concern. The inhibition of bacterial virulence has been proposed as an alte......Staphylococcus aureus infections are becoming increasingly difficult to treat due to antibiotic resistance with the community-associated methicillin-resistant S. aureus (CA-MRSA) strains such as USA300 being of particular concern. The inhibition of bacterial virulence has been proposed...... as an alternative approach to treat multi-drug resistant pathogens. One interesting anti-virulence target is the agr quorum-sensing system, which regulates virulence of CA-MRSA in response to agr-encoded autoinducing peptides. Agr regulation confines exotoxin production to the stationary growth phase...

The siting of UK nuclear reactors.

Science.gov (United States)

Grimston, Malcolm; Nuttall, William J; Vaughan, Geoff

2014-06-01

Choosing a suitable site for a nuclear power station requires the consideration and balancing of several factors. Some 'physical' site characteristics, such as the local climate and the potential for seismic activity, will be generic to all reactors designs, while others, such as the availability of cooling water, the area of land required and geological conditions capable of sustaining the weight of the reactor and other buildings will to an extent be dependent on the particular design of reactor chosen (or alternatively the reactor design chosen may to an extent be dependent on the characteristics of an available site). However, one particularly interesting tension is a human and demographic one. On the one hand it is beneficial to place nuclear stations close to centres of population, to reduce transmission losses and other costs (including to the local environment) of transporting electricity over large distances from generator to consumer. On the other it is advantageous to place nuclear stations some distance away from such population centres in order to minimise the potential human consequences of a major release of radioactive materials in the (extremely unlikely) event of a major nuclear accident, not only in terms of direct exposure but also concerning the management of emergency planning, notably evacuation.This paper considers the emergence of policies aimed at managing this tension in the UK. In the first phase of nuclear development (roughly speaking 1945-1965) there was a highly cautious attitude, with installations being placed in remote rural locations with very low population density. The second phase (1965-1985) saw a more relaxed approach, allowing the development of AGR nuclear power stations (which with concrete pressure vessels were regarded as significantly safer) closer to population centres (in 'semi-urban' locations, notably at Hartlepool and Heysham). In the third phase (1985-2005) there was very little new nuclear development, Sizewell

Determinación de la adsorción de cadmio mediante isotermas de adsorción en suelos agrícolas venezolanos

OpenAIRE

Subero Neudis; Sánchez Nereida; Rivero Carmen

2011-01-01

El cadmio es un metal pesado que tiende a acumularse en la superficie del suelo. En los últimos años, las actividades antropogénicas han ocasionado un incremento en los niveles de este metal en suelos agrícolas generando gran preocupación ambiental debido a su movilidad y lixiviación en el perfil del suelo y a la facilidad con que es absorbido por las plantas. El objetivo de este trabajo fue determinar la capacidad de adsorción de cadmio, de cuatro suelos venezolanos de uso agrícola con difer...

Planning and plutonium. Evidence of the Town and Country Planning Association to the Public Inquiry into an oxide reprocessing plant at Windscale

International Nuclear Information System (INIS)

1978-01-01

The case of the Town and Country Planning Association of Great Britain at the Public Inquiry into the proposed uranium oxide reprocessing plant at Windscale, Cumbria, in the summer of 1977, is presented. The bulk of the book consists of the evidence of the Association's eight witnesses, several of whom have international reputations in their field. The main matters covered by the evidence are the economics of nuclear power compared with other sources of energy; energy demand and supply forecasts in the UK, and the timing and length of the so-called energy gap, together with alternative ways of filling it and the prospects for coal, oil and gas; the risks of proliferation of nuclear weapons; the hazards of low-level radiation to the environment, the general public and workers in nuclear installations, and the inadequacy of current standards; the need for environmental impact analysis before approval is given to major nuclear installations, with reference to United States and British experience; the national, regional and local planning considerations such as employment, housing and visual impact. The evidence is put into context with introductory material on the purpose and terms of reference of the Inquiry, the main events leading up to it, and a general statement of the Association's case. The book ends with a philosophical comment on the alternatives to a plutonium future

Propuesta metodológica interdisciplinaria para el análisis de las relaciones comerciales presentes en el sector agrícola costarricense: el caso del subsector frijolero

Directory of Open Access Journals (Sweden)

Ileana Ávalos

2011-01-01

Full Text Available El complejo entramado de relaciones de poder genera influencia directa en la construcción de políticas públicas agrícolas y en los procesos de intercambio comercial. En un sector tan sensible como el agrícola, cobra mayor relevancia el reconocimiento, identificación y análisis de las relaciones que se estructuran tanto a nivel sectorial como sub-sectorial. Esta disección es la que podría permitir el planteamiento de renovadas políticas públicas y de estrategias asertivas para el sector agrícola. El presente artículo es producto de una investigación científica denominada ?Dinámica de poder en la agrocadena costarricense de frijol: un estudio a partir del Sello de Apoyo al productor nacional de frijol?, la cual describe las relaciones existentes entre grupos económicos, comerciales y sociales dentro de la agrocadena del frijol. Particularmente este artículo realiza una propuesta metodológica para analizar las relaciones de poder en el sector agrícola, tomando como referencia la experiencia adquirida analizando el subsector frijolero costarricense.

Relações contratuais de crédito agrícola e o papel dos agentes financeiros privados: teoria e evidências dos EUA

Directory of Open Access Journals (Sweden)

Fabio R Chaddad

2003-01-01

Full Text Available Este trabalho analisa a questão do financiamento da produção agrícola sob uma ótica sistêmica, considerando o papel dos agentes privados no fornecimento de crédito rural. Desenvolve-se a idéia de que o volume e o custo de recursos financeiros disponibilizados para a produção agrícola são afetados por "fricções" em diversas transações sequenciais interligando emprestadores e tomadores de crédito. O objetivo do trabalho é analisar as vantagens comparativas dos diversos agentes que atuam no mercado de crédito, enfocando o potencial de cada agente em reduzir as tais fricções. Esta análise comparativa baseia-se na leitura do funcionamento do mercado de crédito agrícola dos Estados Unidos e pode ser aplicada nara o desenvolvimento de novos arranjos contratuais no mercado brasileiro.

Safety

International Nuclear Information System (INIS)

Jones, P.M.S.

1987-01-01

Aspects of fission reactors are considered - control, heat removal and containment. Brief descriptions of the reactor accidents at the SL-1 reactor (1961), Windscale (1957), Browns Ferry (1975), Three Mile Island (1979) and Chernobyl (1986) are given. The idea of inherently safe reactor designs is discussed. Safety assessment is considered under the headings of preliminary hazard analysis, failure mode analysis, event trees, fault trees, common mode failure and probabalistic risk assessments. These latter can result in a series of risk distributions linked to specific groups of fault sequences and specific consequences. A frequency-consequence diagram is shown. Fatal accident incidence rates in different countries including the United Kingdom for various industries are quoted. The incidence of fatal cancers from occupational exposure to chemicals is tabulated. Human factors and the acceptability of risk are considered. (U.K.)

The status of spent fuel storage in the UK

International Nuclear Information System (INIS)

Dunn, M.J.; Topliss, I.R.

1999-01-01

Nuclear generating capacity in the UK is static with no units currently under construction. There are three main nuclear fuel types used in the UK for Magnox reactors, AGRs and PWRs. All Magnox fuel will ultimately be reprocessed following a short period of interim storage. AGR fuel will either be reprocessed or long term stored in ponds. PWR fuel will be stored underwater at the reactor site for the foreseeable future, with no decision as yet made to its ultimate management route. (author)

Modelo Evolucionário de Aprendizado Agrícola

Directory of Open Access Journals (Sweden)

José Maria Ferreira da Silveira

2011-11-01

Full Text Available The definition of the agriculture sector as a supplier dominated is a very restrictive supposition which implies that the technological changes would be residual. The learning process of the farmer throughout, determines the increase in productivity, and simultaneously the reduction in the cost of production, which all depends on the ability of the producers to recognize the value of new information, as well as the managerial ability to apply technological knowledge. The investments in the managerial capability of the farmers allow taking better advantage of the external knowledge. With the aim of systemizing the chains of the main ideas on agricultural dynamics, one has sought to construct the Evolutionary Model of Learning. Preliminary results showed that innovative producers on average maintain an avant-garde technological stance. The increase in the absorptive capacity serves to conquer gains in production and to make lower costs.A definição do setor agrícola como sendo dominado pelos fornecedores é uma pressuposição muito restritiva, já que define a mudança tecnológica como residual. O processo de aprendizado do agricultor no decorrer do tempo é responsável pelo aumento da produtividade e, paralelamente, pela redução dos custos de produção, dependendo da capacidade do produtor de interpretar e assimilar as novas informações, bem como da habilidade gerencial do uso do conhecimento tecnológico. Os investimentos na capacidade gerencial dos agricultores possibilitam um melhor aproveitamento do conhecimento externo. No intuito de sistematizar o encadeamento das principais ideias da dinâmica agrícola, buscou-se construir o modelo evolucionário de aprendizado. Os resultados preliminares mostraram que os produtores inovadores, em média, mantêm posições de vanguarda tecnológica. O aumento da capacidade de absorção auxilia nos ganhos produtivos e nas quedas dos custos.

Conditioning for definitive storage of radioactive graphite bricks from reactor decommissioning

International Nuclear Information System (INIS)

Costes, J.R.; Koch, C.; Tassigny, C. de; Vidal, H.; Raymond, A.

1990-01-01

The decommissioning of gas-graphite reactors in the EC (e.g. French UNGGs, British Magnox reactors and AGRs, and reactors in Spain and in Italy) will produce large amounts of graphite bricks. This graphite cannot be accepted without particular conditioning by the existing shallow land disposal sites. The aim of the study is to examine the behaviour of graphite waste and to develop a conditioning technique which makes this waste acceptable for shallow land disposal sites. 18 kg of graphite core samples with an outside diameter of 74 mm were removed from the G2 gas-cooled reactor at Marcoule. Their radioactivity is highly dependent on the position of the graphite bricks inside the reactor. Measured results indicate an activity range of 100-400 MBq/kg with 90% Tritium, 5% 14 C, 3% 60 Co, 1.5% 63 Ni. Repeated porosity analyses showed that open porosity ranging from 0 to 100 μm exceeded 23 vol% in the graphite. Water penetration kinetics were investigated in unimpregnated graphite and resulted in impregnation by water of 50-90% of the open porosity. Preliminary lixiviation tests on the crude samples showed quick lixidegree of Cs (several per cent) and of 60 Co, and 133 Ba at a lesser degree. The proposed conditioning technique does not involve a simple coating but true impregnation by a tar-epoxy mixture. The bricks recovered intact from the core by robot services will be placed one by one inside a cylindrical metallic container. But this container may corrode and the bricks may become fragmented in the future, the normally porous graphite will be unaffected by leaching since it is proved that all pores larger than 0.1 μm will be filled with the tar-epoxy mixture. This is a true long-term waste packaging concept. The very simple technology required for industrial implementation is discussed

Electron Microscopic Examination of Irradiated TRISO Coated Particles of Compact 6-3-2 of AGR-1 Experiment

Energy Technology Data Exchange (ETDEWEB)

Van Rooyen, Isabella Johanna [Idaho National Lab. (INL), Idaho Falls, ID (United States); Demkowicz, Paul Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States); Riesterer, Jessica Lori [Idaho National Lab. (INL), Idaho Falls, ID (United States); Miller, Brandon Douglas [Idaho National Lab. (INL), Idaho Falls, ID (United States); Janney, Dawn Elizabeth [Idaho National Lab. (INL), Idaho Falls, ID (United States); Harp, Jason Michael [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ploger, Scott Arden [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2012-12-01

The electron microscopic examination of selected irradiated TRISO coated particles of the AGR-1 experiment of fuel compact 6-3-2 are presented in this report. Compact 6-3-2 refers to the compact in Capsule 6 at level 3 of Stack 2. The fuel used in capsule 6 compacts, are called the “baseline” fuel as it is fabricated with refined coating process conditions used to fabricate historic German fuel, because of its excellent irradiation performance with UO₂ kernels. The AGR-1 fuel is however made of low-enriched uranium oxycarbide (UCO). Kernel diameters are approximately 350 µm with a U-235 enrichment of approximately 19.7%. Compact 6-3-2 has been irradiated to 11.3% FIMA compact average burn-up with a time average, volume average temperature of 1070.2°C and with a compact average fast fluence of 2.38E21 n/cm

Efeito de doses de gesso agrícola na cultura do milho e alterações químicas no solo

Directory of Open Access Journals (Sweden)

Luiz Augusto Amaral

2017-04-01

Full Text Available A cultura do milho apresenta importância econômica no cenário agrícola, de modo que a região Centro Oeste detém a maior media de produtividade do Brasil. O objetivo deste estudo foi avaliar o efeito de doses de gesso agrícola sobre a produtividade de milho cultivado em segunda safra e seus efeitos químicos no solo. O experimento foi realizado no Campus experimental da UNEMAT, Tangará da Serra – MT. O delineamento experimental foi em blocos casualizados (DBC com cinco tratamentos (0 kg ha-1, 1.000 kg ha-1, 2.000 kg ha-1, 3.000 kg ha-1 e 4.000 kg ha-1 de gesso agrícola com quatro repetições, totalizando 20 parcelas. Foi utilizado o híbrido de milho DKB 390 VT Pro2, e as parcelas foram constituídas de cinco metros de comprimento por quatro de largura, com espaçamento entre linhas de 0,50 m. Foi aplicado calcário dolomítico e gesso agrícola aos 60 e 30 dias antes da semeadura, respectivamente. Somente a variável diâmetro do caule e produtividade apresentou diferença significativa entre os tratamentos, onde os diâmetros superiores foram observados nas doses acima 2.000 kg ha-1 e a maior produtividade obtida na dose de 4.000 kg ha-1 de gesso. O efeito da aplicação do gesso proporcionou aumento na concentração de enxofre, cálcio e magnésio no subsolo, assim como redução nos teores de alumino. A dose de 4.000 kg ha-1 de gesso promoveu a maior produtividade.

Modernização da Agricultura em Moçambique: determinantes da renda agrícola

Directory of Open Access Journals (Sweden)

Carlos E. Guanziroli

2015-03-01

Full Text Available O objetivo deste trabalho é verificar até que ponto as tecnologias oriundas da revolução verde foram efetivamente adotadas na África Subsaariana e, nos casos em que foram adotadas, se tiveram sucesso em melhorar a renda e a produtividade da agricultura. Para este fim, o trabalho faz primeiramente um breve resumo do estado das artes da revolução verde na África, mostrando quais países avançaram mais e como se correlaciona a utilização de fertilizantes químicos com os aumentos de produtividade. Faz-se também uma discussão sobre as características do processo de intensificação num caso em particular, o de Moçambique. Finalmente, com base nos microdados do Tratado de Inquérito Agrícola (TIA, se testa um modelo econométrico de MQO que visa avaliar os determinantes da renda agrícola e, em particular, do uso de fertilizantes químicos.

Plantas forrageiras cultivadas em assentamentos da reforma agrária visando mapear para o melhoramento participativo

Directory of Open Access Journals (Sweden)

Maria Tereza Bolzon Soster

2014-05-01

Full Text Available O presente trabalho visou atender a demanda de levantamento sobre as plantas forrageiras cultivadas em assentamentos da Reforma Agrária no Rio Grande do Sul para que um projeto de Melhoramento Participativo possa ser implantado para esse fim. Os dados foram levantados através dos alunos do Instituto Educar e seus assentamentos, totalizando 8 assentamentos, abrangendo 1019 famílias. Em média têm-se 16 espécies forrageiras por assentamento, entre espécies de inverno e de verão, com maior destaque à espécies de verão e maior contribuição de gramíneas (Poaceae. Notou-se que quanto maior o assentamento, mais espécies estão à disposição dos mesmos, enfatizando a importância da fragmentação agrária para a biodiversidade, inclusive de cultivos de plantas forrageiras. Os agricultores se demonstraram receptivos a programas de melhoramento de suas pastagens sobretudo quanto a adaptação e rendimento de massa seca. 

The development of advanced gas cooled reactor iodine adsorber systems

International Nuclear Information System (INIS)

Meddings, P.

1986-01-01

Advanced Gas Cooled Reactors (AGRs) are provided with plants to process the carbon dioxide coolant prior to its discharge to atmosphere. Included in these are beds of granular activated charcoal, contained within a suitable pressure vessel, through which the high pressure carbon dioxide is passed for the purpose of retaining iodine and iodine-containing compounds. Carry-over carbon dust from the adsorption beds was identified during active in-situ commissioning testing, radio-iodine being transported with the particulate material due to gross disturbance of the adsorber carbon bed and displacement of the vessel internals. The methods used to identify the causes of the problems and find solutions are described. A development programme for the Heysham-2 and Torness reactors iodine adsorber units was set up to identify a method of de-dusting granular charcoal and develop it for full-scale use, of assess the effect under conditions of high gas density of approach velocity on charcoal fines production and to establish the pressure drop characteristics of a packed granular bed and to develop an effective design of inlet gas diffuser manifold to ensure an acceptable velocity distribution. This has involved the construction of a small scale high pressure carbon dioxide rig and development of an air flow model. This work is described. (UK)

Etiam specie inanium validus (Anais, XIII, 8, 3): o papel de Agrícola e Corbulão na narrativa de Tácito.

OpenAIRE

Aguiar, Mariana Alves de

2013-01-01

Programa de Pós-Graduação em História. Departamento de História, Instituto de Ciências Humanas e Sociais, Universidade Federal de Ouro Preto. A presente dissertação trata da análise do papel de dois generais presentes na narrativa de Tácito, Agrícola e Corbulão. O primeiro general encontra-se em uma biografia, Vida de Agrícola, e o segundo em uma narrativa histórica, os Anais de Tácito. Tácito nos apresenta esses generais como uma forma de exemplo de conduta aristocrática imperial. Pensamo...

Del hogar agrícola a los maestros queseros. La escuela granja de Tandil (Argentina, 1915-1960

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Talía Violeta Gutiérrez

2015-01-01

Full Text Available La formación de recursos humanos y la generación de conocimientos adaptados a las condiciones de explotación de las diversas produccio-nes regionales en la Argentina ocuparon la atención de los técnicos del Ministerio de Agricultura de la Nación, de las entidades agraristas y de sectores políticos y educativos diversos desde inicios del siglo XX. No escapó a ese interés la preocupación por la mujer y el “hogar agrícola”. En el presente artículo fueron analizadas, en ese contexto, las primeras décadas de la Escuela Granja “Ramón Santamarina” de Tandil, un esta-blecimiento con una rica historia institucional que albergó la primera es-cuela del hogar agrícola del país, transformada pronto en granja-escuela y especializada en industria láctea. El tránsito del “hogar agrícola” a la preparación de maestros queseros -en el marco de la orientación productivista de las escuelas en la pro-puesta educativa del Ministerio-, los sujetos sociales involucrados, la es-pecialización en quesería y sus resultados, son algunas de las cuestiones analizadas. Esto se inserta en el contexto de un proyecto educativo agra-rio pensado no solo como fuente de mano de obra, vinculado a determi-nadas industrias agrarias, sino también –y tal vez más que nada– como irradiador de ese tipo de enseñanzas hacia la comunidad.

Histórico e os limites da reforma agrária na contemporaneidade brasileira History and limits of the agrarian reform in the Brazilian contemporary time

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Paulo Nakatani

2012-06-01

Full Text Available Objetiva-se reconstituir a trajetória da questão fundiária (e agrária na experiência de maior concentração de riqueza e recursos vivenciada no âmbito do sistema capitalista, partindo-se da premissa de que a crescente desigualdade do modelo brasileiro passa necessariamente pela questão agrária. Num segundo momento, procede-se à análise dos limites atualmente colocados a qualquer possibilidade de uma Reforma Agrária ampla e estrutural, dados pelo avanço do agronegócio nos últimos dez anos, pela desmobilização política de parcela significativa da sociedade no que se refere a esta questão e pelos próprios limites estruturais da economia brasileira nos quadros da globalização financeira. O texto será dividido em seis sessões: a colonização e origens do latifúndio; b O modelo agroexportador e a ruptura incompleta; c a questão agrária e a industrialização brasileira; d a questão agrária e o agronegócio; e os limites da reforma agrária na contemporaneidade; f considerações finais.This paper aims at reconstructing the history of the land (agrarian issue considering the greatest concentration of wealth and resources in the capitalist system. The standpoint is that the growing inequality of the Brazilian model is related to the agrarian issue. Secondly, we analyze the limits ­currently placed on any possibility of a comprehensive and structural agrarian reform, due to the advancement of the agribusiness over the last ten years, the political demobilization of a significant portion of society that put this issue aside, and the limits of the Brazilian economy in the context of the financial globalization. The paper is divided into six parts: a colonization and origins of the large landed estates; b the agro-export model and the incomplete rupture; c the agrarian issue and the Brazilian industrialization; d the agrarian issue and the agribusiness; e the limits of the agrarian reform in the contemporary time; f final

Proyección para la instalación de una empresa de servicios agrícolas y administrativos en Manabí

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Carlos Oswaldo Balarezo Beltrón

2016-06-01

Full Text Available La investigación se realizó en los cantones Bolívar, Chone y Tosagua. El objetivo fue establecer la proyección de implantación de una empresa de servicios agrícolas y administrativos. La metodología se dividió en cuatro etapas: diagnóstico, análisis estratégico, programa de asistencia y socialización. Entre los principales cultivos de la zona se encontraron al cacao, tomate y plátano. Se determinó que problemas de sanidad vegetal, como hongos e insectos fueron los más importantes. La mayoría de los encuestados consideraron que necesitan un programa de asistencia administrativa que les ayude a planificar sus actividades. Los especialistas señalaron que la asistencia agrícola que se necesita es sobre control de plagas y pequeños sistema de riego. Los temas expuestos en la socialización fueron manejo integrado de plagas, aplicación de sistema de riego por goteo, manejo de fertilización y planificación estratégica en la finca. Palabras clave: Economía agrícola, ambiental, innovación tecnológica, ecológico, control.

Frequency and distribution of leakages in steam generators of gas-cooled reactors

International Nuclear Information System (INIS)

Bongratz, R.; Breitbach, G.; Wolters, J.

1988-01-01

In gas cooled reactors with graphitic primary circuit structures - such as HTR, AGR or Magnox - the water ingress is an event of great safety concern. Water or steam entering the primary circuit react with the hot graphite and carbon-oxide and hydrogen are produced. As the most important initiating event a leak in a steam generator must be taken into account. From the safety point of view as well as for availability reasons it is necessary to construct reliable boilers. Thus the occurrence of a boiler leak should be a rare event. In the context of a probabilistic safety study for an HTR-Project much effort was invested to get information about the frequency and the size distribution of tube failures in steam generators of gas cooled reactors. The main data base was the boiler tube failure statistics of United Kingdom gas cooled reactors. The data were selected and applied to a modern HTR steam generator design. A review of the data showed that the failure frequency is not connected with the load level (pressures, temperatures) or with the geometric size of the heating surface of the boiler. Design, construction, fabrication, examination and operation conditions have the greatest influence an the failure frequency but they are practically not to be quantified. The typical leak develops from smallest size. By erosion effects of the entering water or steam it is enlarged to perhaps some mm 2 , then usually it is detected by moisture monitors. Sudden tube breaks were not reported in the investigated period. As a rule boiler leaks in gas cooled reactors are much more, rare then leaks in steam generators of light water reactors and fossil fired boilers. (author)

Scottish Nuclear, the company

International Nuclear Information System (INIS)

Yeomans, R.M.

1991-01-01

A former chief executive of Scottish Nuclear, formed when United Kingdom electricity generation was privatized, describes the financial viability of the company and considers the future of nuclear power. Scottish Nuclear owns and operates the Advanced Gas Cooled (AGR) and Magnox reactors at Hunterston and the AGR reactor at Torness and is a separate company from those dealing with hydro-electric and non-nuclear generation of electricity. Costs of running the reactors is identified as a proportion of the whole for certain key issues such as station costs, depreciation, decommissioning and insurance. While nuclear power generation using outmoded Magnox reactors is costly, the ecological cost of global warming is seen as more of a problem. Future policy for nuclear power in Scotland must include new plant, probably pressurized water reactors and a clear policy of safety enhancement. (UK)

Presence of Classical Enterotoxin Genes, agr Typing, Antimicrobial Resistance, and Genetic Diversity of Staphylococcus aureus from Milk of Cows with Mastitis in Southern Brazil.

Science.gov (United States)

Kroning, Isabela S; Iglesias, Mariana A; Mendonça, Karla S; Lopes, Graciela V; Silva, Wladimir P

2018-05-01

Staphylococcus aureus is a common causative agent of bovine mastitis in dairy cows and commonly associated with foodborne disease outbreaks. The aim of this study was to evaluate the presence of enterotoxin genes, agr typing, antimicrobial resistance, and genetic diversity of S. aureus isolated from milk of cows with mastitis in dairy farms from southern Brazil. Results showed that 7 (22.6%) of 31 S. aureus isolates were positive for enterotoxin genes. Specifically, the genes encoding for enterotoxins A ( n = 4), C ( n = 2), and B ( n = 1) were detected. Isolates belonging to the agr group III (10 of 31, 32.2%) and agr group I (7 of 31, 22.5%) were the most common. To our knowledge, this is the first report of both agr I and III in the same S. aureus isolate from milk of cows with bovine mastitis. The antimicrobial resistance test showed that 54% of the isolates were multiresistant to antimicrobial agents. The macrorestriction analysis produced 16 different major SmaI pulsed-field gel electrophoresis patterns, with up to two subpatterns. Moreover, the presence of some S. aureus clones in a distinct area was observed. Although this study characterized a limited number of S. aureus isolates, the presence of classical enterotoxin genes and resistance to multiple antimicrobial agents reinforces the importance of this microorganism to animal and human health. In addition, similar genetic profiles have been identified in distinct geographic areas, suggesting clonal dissemination of S. aureus in dairy herds from southern Brazil.

Incentivos a la innovación de la biotecnología agrícola-alimentaria en México

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Marcela Amaro-Rosales

2015-01-01

Full Text Available En el artículo analizamos la innovación biotecnológica relacionada con los sectores agrícola y alimentario en México. Tomamos en cuenta las políticas públicas, las leyes y las reglamentaciones; la dinámica del sector y del merado. Asimismo, analizamos la forma en la que las empresas agro-alimentarias pueden aprovechar los insumos de conocimiento científico y tecnológico que ofrece la biotecnología. La principal conclusión es que actualmente el marco institucional regulatorio y la dinámica del mercado establecen más barreras que incentivos para el desarrollo y aplicación de innovaciones biotecnológicas y con ello lograr una mejora en la cali - dad de los alimentos y un incremento en la competitividad de las empresas y del sector agrícola en el país.

Morbilidad laboral en el sector agrícola en trabajadores afiliados a una administradora de riesgos laborales (ARL) de Colombia, durante el periodo 2011-2012.

OpenAIRE

Velásquez Bueno, Diana Marcela

2013-01-01

Este estudio muestra la prevalencia por enfermedad laboral de un grupo de trabajadores afiliados a una ARL en Colombia. Compara la morbilidad laboral entre dos grupo de trabajadores expuestos y no expuestos al trabajo agrícola y al interior del grupo de trabajadores agrícolas agrupados en las actividades de corte de caña, cultivo de banano y flores. Se realizó un estudio descriptivo de tipo transversal durante el periodo 2011-2012, mediante la revisión de una base de datos de morbilidad la...

Aspectos constitucionais do direito agrário emenda constitucional N° 10/64

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José Carlos Vieira

1988-07-01

Full Text Available This paper, presents a brief history of the constitutional work applied to property rights in Brazil, mainly to those regarding land property. lt also shows the development of agrarian rights as an independent branch of the juridical prescription up to its effective recognition. It slightly shows the important role of the social function of property in constitutional texts as to support governmental actions aiming at an agrarian reform, and any other tendency to alter the rural profile of the country. This work is aimed to show that, despite a set of laws related to the agrarian reality of this country, the facts and data make it clear that nothing has been done about it up to today. The research Our constitutional texts shows that some advances towards the effectiveness of the social function of property principles have been made; nevertheless, the constitution to be promulgated by the year 1988, surprisingly takes a step backwards as to this chapter for it decreases the scope that it had in former constitutions and even in the original ones by authoritarian governments.O presente trabalho contém um resumo histórico do tratamento constitucional reservado ao direito de propriedade no Brasil, especialmente à propriedade da terra, bem assim a evolução do direito agrário como ramo autônomo do ordenamento jurídico, até o seu efetivo reconhecimento como tal. Registra, mesmo que rapidamente, a importância que teve a adotação do princípio da "função social da propriedade" nos textos constitucionais, de forma a respaldar ações governamentais objetivando a realização da reforma agrária e outras medidas tendentes a alterar o perfil rural do país. O trabalho procura mostrar, também, que, malgrado dispor o pais de um rol de leis capazes de dar suporte a propostas destinadas a promover uma efetiva mudança na realidade agrária, os fatos demonstram claramente que isto não ocorreu até hoje. A pesquisa nos textos constitucionais mostra

Marketing in the pre-development process of agricultural machines: a reference model Marketing no pré-desenvolvimento de máquinas agrícolas: um modelo de referência

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Alexandre S. de Oliveira

2012-08-01

Full Text Available The theme of the research is the development of the domain of marketing knowledge in the design of agricultural machinery. It is developed throughout the design of agricultural machinery in order to identify the corporate and customers needs and to develop strategies to satisfy these needs. The central problem of the research questions which marketing tools to apply on pre-development process of farm machinery, in order to increase the market value of the products and of the company and, consequently, generate competitive advantage to the manufacturers of agricultural machinery. As methodology, it was developed bibliographical research and multicase study of the development process of agricultural machinery developed by small, medium and large companies and the academy. As a result, a marketing reference model was elaborated for the pre-development stage of agricultural machinery, which outlines the activities, tasks, mechanisms and controls that can be used in strategic planning and in products planning of agricultural machinery manufacturers, contributing to explain the explicit knowledge in the marketing field.O tema de pesquisa é o desenvolvimento do domínio de conhecimento de marketing no projeto de máquinas agrícolas. Este é desenvolvido ao longo do projeto de máquinas agrícolas a fim de identificar as necessidades dos clientes e da corporação e criar estratégias para que sejam satisfeitas. O problema central de pesquisa questiona quais mecanismos de marketing utilizar no processo de pré-desenvolvimento de máquinas agrícolas, para aumentar o valor de mercado dos produtos e da empresa e, conseqüentemente, gerar um diferencial competitivo às fabricantes de máquinas agrícolas. Como metodologia desenvolveu-se pesquisas bibliográficas e estudo de multicasos do processo de desenvolvimento de máquinas agrícolas desenvolvido pelas pequenas, médias e grandes empresas e pela academia. Como resultado elaborou-se um modelo

Obreros agrícolas migrantes en Sinaloa

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Florencio Posadas Segura

2015-01-01

Full Text Available el objetivo de este artículo es demostrar la presencia sig-nificativa de los obreros agrícolas migrantes, algunas carac-terísticas que la explican y la pauperización que experimen-tan. La causa principal de la migración es la desocupación;los empresarios controlan los métodos de contratación, tras-portación y explotación, y los jornaleros rurales migrantestrabajan más, ganan menos y su situación es mayormentemiserable. Esto se ilustra con el caso de Villa Benito Juárez,Sinaloa, que prueba la gran importancia de los asalariadosestacionales del campo, como auténticos productores de lariqueza, y la paradoja de su condición de pobreza aguda. Elpatrón migratorio interno y externo descubierto contradicelos estereotipos prevalecientes, en el marco de la reestruc-turación productiva y laboral de la agricultura mexicana yla incorporación de fuerza de trabajo asalariada pagada pordebajo de su valor, segmentada y dosificada conveniente-mente de acuerdo con la estrategia del capital, guiada por elespíritu de la ganancia máxima.

Estimación de la movilidad del ibuprofeno en suelos agrícolas

OpenAIRE

Biel Maeso, Miriam

2011-01-01

Los productos farmacéuticos y de higiene personal están emergiendo como contaminantes en el medio ambiente, lo que conlleva una creciente preocupación en la conciencia de la población. La mayoría de los estudios sobre el destino ambiental de estos productos se han centrado en los procesos de tratamiento de las aguas residuales, en los ambientes acuáticos, y en los lodos de depuración, sin embargo, poco se sabe acerca de su comportamiento en los suelos agrícolas. Máster Universitario en Hid...

The development of calculational methods and assessment standards for AGR refuelling safety cases

International Nuclear Information System (INIS)

Dawson, J.W.; Grant, R.J.; Thomas, D.L.

1995-01-01

This paper considers the methods used to assess the protection needed against hazards in the AGR fuel route. These methods are all directed towards the objective of showing that all postulated events taking place during refuelling are acceptable within agreed criteria of severity versus frequency. The methods allow the determination of temperatures arising in various hazards, from which estimates can be made of the radiological release, if any, which would occur. Comparison of this estimate with the level considered acceptable at the fault frequency leads to the requirement for protection. (author)

Radioactive metals disposal and recycling impact modelling

International Nuclear Information System (INIS)

Kemp, N.W.; Lunn, R.J.; Belton, V.; Kockar, I.

2014-01-01

Screening life cycle assessment models developed to investigate hypothetical disposal and recycling options for the Windscale Advanced Gas-cooled Reactor heat exchangers were used to generate more complex models addressing the main UK radioactive metals inventory. Both studies show there are significant environmental advantages in the metals recycling promoted by the current low level waste disposal policies, strategies and plans. Financial benefits from current metals treatment options are supported and offer even greater benefits when applied to the UK radioactive metals inventory as a whole. (authors)

La sucesión "mortis causa" en la explotación agrícola familiar

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José Luis De Los Mozos

2015-01-01

Full Text Available Llevo nada menos que cuarenta años dando vueltas al tema de la sucesión mortis causa en el Derecho agrario y más concretamente, al de la sucesión en la explotación agrícola. Esto no constituye ningún mérito, naturalmente, no es más que una mera circunstancia que acredita, cuando mucho, la firmeza de una convicción. Durante este tiempo, con mayor o menor contacto con la realidad social, he seguido y sigo fiel a mis puntos de vista originarios; no es que nada haya cambiado en todos estos años, sino que ha cambiado casi todo.Pero es que las soluciones que me parecían entonces muy dudosas, ahora me parecen inadmisibles.La evolución económica y social, ha puesto de relieve que las ideas que se utilizaban hace medio siglo en la materia, actualmente han quedado obsoletas (...Contenido: Una distinción obligada y un recuerdo inevitable. El recurso a la atribución preferente. Las condicionantes de la atribución preferente. El concepto de explotación agrícola. La reforma del derecho sucesorio como recapitulación

Avaliação económica de tarifas de água no uso agrícola: um estudo de caso no Sul de Portugal

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Rui Fragoso

2009-09-01

Full Text Available Este artigo avalia os efeitos de políticas de tarifas da água no uso agrícola, em termos do consumo de água, do aproveitamento das áreas beneficiadas com regadio, do rendimento do produtor agrícola, da recuperação dos custos com a água e do desenvolvimento agrícola. A metodologia utilizada baseia-se na elaboração de um modelo de programação matemática multiperíodo, adaptado às características específicas de uma empresa agrícola do Sul de Portugal. Foram analisadas a tarifa fixa por área beneficiada, a tarifa volumétrica por metro cúbico de água consumida, a tarifa binómica e a tarifa progressiva. Para as simulações, foram considerados um cenário produtivo tradicional e um cenário produtivo alternativo, em que são introduzidas culturas de valor acrescentado.This paper evaluates the effects of water tariffs in irrigation, in terms of water consumption, land irrigated, farm income, water cost recovery and agricultural investment. The methodology is based on a multiperiod mathematical programming model, which was applied to the specific characteristics of a representative farm in southern Portugal. The main aspects analyzed were: the fix tariff per area benefited, the volumetric tariff per cubic meter of water consumed, the mix tariff and the increasing block tariff. For the simulations, it was considered a traditional productive scenario and an alternative scenario, which include value added crops.

Modelo para el monitoreo y seguimiento de indicadores de sostenibilidad del recurso hídrico en el sector agrícola

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Carvajal Escobar Yesid

2011-12-01

Full Text Available El sistema de monitoreo y seguimiento permite identificar, a través de indicadores e índices, la sostenibilidad del recurso hídrico en el sector agrícola de la microcuenca Centella (Dagua-Valle del Cauca. Este modelo de monitoreo permite evaluar continua y sistemáticamente el progreso y los cambios ocasionados por la ejecución de un conjunto de actividades en un período de tiempo determinado. De igual manera, a través de este sistema es posible realizar un seguimiento y verificar en qué medida se cumplen las metas propuestas de sostenibilidad del recurso hídrico en el sector agrícola a nivel: biofísico, tecnológico, político-institucional y socioeconómico.

Modelo para el monitoreo y seguimiento de indicadores de sostenibilidad del recurso hídrico en el sector agrícola

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Wilmar Loaiza Cerón

2011-01-01

Full Text Available El sistema de monitoreo y seguimiento permite identificar, a través de indicadores e índices, la sostenibilidad del recurso hídrico en el sector agrícola de la microcuenca Centella (Dagua-Valle del Cauca. Este modelo de monitoreo permite evaluar continua y sistemáticamente el progreso y los cambios ocasionados por la ejecución de un conjunto de actividades en un período de tiempo determinado. De igual manera, a través de este sistema es posible realizar un seguimiento y verificar en qué medida se cumplen las metas propuestas de sostenibilidad del recurso hídrico en el sector agrícola a nivel: biofísico, tecnológico, político-institucional y socioeconómico.

Trabalhismo, reforma agrária, legislação para as populações rurais: uma abordagem do projeto político de Fernando Ferrari

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Ricardo Oliveira da Silva

2015-05-01

Full Text Available No presente texto, apresentamos uma abordagem introdutória do projeto político de Fernando Ferrari para a questão agrária. Ao longo da década de 1950 e começo dos anos de 1960, esse autor participou das discussões em torno dos problemas rurais brasileiros com base na doutrina trabalhista, desenvolvida por Alberto Pasqualini. Nesse sentido, destacamos o projeto trabalhista defendido por Fernando Ferrari para o campo mediante dois temas constantes em seus escritos: a reforma agrária e a legislação para a população rural.

Inspeção periódica de pulverizadores agrícolas

OpenAIRE

Gandolfo, Marco Antonio [UNESP

2001-01-01

Para a otimização no uso de agroquímicos, vários países tem realizado avaliações periódicas em pulverizadores agrícolas. No Brasil, o reconhecimento do estado destas máquinas, pode nortear pesquisas e investimentos em orientação de uso e manutenção. Os objetivos deste trabalho foram avaliar o estado de pulverizadores em uso na agricultura nacional, estudar a necessidade de implantação de inspeções periódicas em tais máquinas no Brasil e desenvolver metodologia específica para as condições bra...

O direito do comércio internacional no setor agrícola

OpenAIRE

D'Ávila, André Luiz Bettega

2006-01-01

Dissertação (mestrado) - Universidade Federal de Santa Catarina, Centro de Ciências Jurídicas. Programa de Pós-Graduação em Direito. A dissertação analisa a regulamentação jurídica dos subsídios agrícolas à exportação na Organização Mundial do Comércio (OMC) e objetiva destacar pontos-chave para ação e pesquisa jurídica sobre o tema no contexto das negociações multilaterais em curso na Rodada Doha. A pesquisa encontra lastro nos Acordos e na jurisprudência da OMC, na doutrina estrangeira, ...

Economía de Producción Agrícola en Colombia: Capitulo 1. Regiones Geográficas y Agrícolas de Colombia

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Beltrán G. Gregorio

1953-09-01

y en su parte sur vuelve a ser plana. La cría del ganado parece ser la ocupación principal; se concentra en los alrededores de Villavicencio. Se han hecho varios intentos espontáneos para colonizar parte de esta región pero sin resultados definitivos. Al tratar sobre la agricultura de un país se hace necesario tomar en cuenta la distribución de sus recursos humanos. La población de Colombia es de unos 10 habitantes por kilometro cuadrado, pero esta cifra global no da ni siquiera una idea aproximada de cómo está poblado el país, ya que más del 98 por ciento de su población vive en el tercio occidental de la nación aun dentro de esta zona la fluctuación por departamentos es bastante grande. Por otro lado están las zonas agrícolas pues hemos visto distintas clasificaciones del país en zonas fitogeográficas y de elevación. Sin embargo éstas no tienen un valor económico inmediato. Dentro de ellas existen regiones más pequeñas pero más homogéneas en cuanto al clima, régimen de lluvias, suelos y organización que se especializan en la producción de uno o más agrícolas. Estas regiones deberán servir en el futuro como núcleo de los estudios de economía de producción agrícola, por tener todas ellas sistemas de agricultura más o menos conocidos pero cuya verdadera organización económica se desconoce. Como en el país no se han hecho todavía estudios serios de geografía económica y las publicaciones de la Contraloría General de la República en este campo se han limitado a una recopilación de los pocos datos estadísticos que se disponen los departamentos, se dan las siguientes descripciones de las zonas agrícolas para que se tenga una idea aproximada de sus principales características.

Detection and Analysis of Particles with Failed SiC in AGR-1 Fuel Compacts

International Nuclear Information System (INIS)

Hunn, John D.; Baldwin, Charles A.; Gerczak, Tyler J.; Montgomery, Fred C.; Morris, Robert N.; Silva, Chinthaka M.; Demkowicz, Paul A.; Harp, Jason M.; Ploger, Scott A.

2014-01-01

As the primary barrier to release of radioactive isotopes emitted from the fuel kernel, retention performance of the SiC layer in tristructural isotropic (TRISO) coated particles is critical to the overall safety of reactors that utilize this fuel design. Most isotopes are well-retained by intact SiC coatings, so pathways through this layer due to cracking, structural defects, or chemical attack can significantly contribute to radioisotope release. In the US TRISO fuel development effort, release of "1"3"4Cs and "1"3"7Cs are used to detect SiC failure during fuel compact irradiation and safety testing because the amount of cesium released by a compact containing one particle with failed SiC is typically ten or more times higher than that released by compacts without failed SiC. Compacts with particles that released cesium during the AGR-1 irradiation test or post-irradiation safety testing at 1600– 1800°C were identified, and individual particles with abnormally low cesium retention were sorted out with the ORNL Irradiated Microsphere Gamma Analyzer (IMGA). X-ray tomography was used for three-dimensional imaging of the internal coating structure to locate low-density pathways through the SiC layer and guide subsequent materialography by optical and scanning electron microscopy. All three cesium-releasing particles recovered from as-irradiated compacts showed a region where the inner pyrocarbon (IPyC) had cracked due to radiation-induced dimensional changes in the shrinking buffer and the exposed SiC had experienced concentrated attack by palladium; SiC failures observed in particles subjected to safety testing were related to either fabrication defects or showed extensive Pd corrosion through the SiC where it had been exposed by similar IPyC cracking. (author)

Seroprevalencia de brucelosis en trabajadores agrícolas de las comarcas costeras de Castellón, España

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Villamarín-Vázquez José Luis

2002-01-01

Full Text Available Objetivo. Determinar la seroprevalencia de brucelosis en trabajadores agrícolas. Material y métodos. Estudio transversal efectuado durante 1996 y 1997 en la Unidad de Salud Laboral del Centro de Salud Pública (CSP de Castellón, España, con 482 aspirantes a su acreditación como manipulador de plaguicidas para aplicación agrícola y a quienes se les hicieron las pruebas serológicas de rosa de Bengala, seroaglutinación de Wright y Coombs antibrucela. En el análisis estadístico se estimó la prevalencia y se usó regresión logística. Resultados. 15 personas (3.1%, IC 95% 1.8%-5.1% presentaron títulos de 1/40 o mayores a las pruebas de Wright o Coombs, y todas negativas al rosa de Bengala. No se apreció riesgo profesional elevado. Conclusiones. La prevalencia estimada fue baja.

On the use of flux-adjoint condensed nuclear data for 1-group AGR kinetics

International Nuclear Information System (INIS)

Hutt, P.K.

1979-03-01

Following previous work on the differences between one and two neutron group AGR kinetics the possible advantages of flux-adjoint condensed lattice data over the simple flux condensation procedure are investigated. Analytic arguments are given for expecting flux-adjoint condensation to give a better representation of rod worth slopes and flux shape changes associated with partially rodded cores. These areas have previously been found to yield most of the one to two neutron group differences. The validity of these arguments is demonstrated comparing various calculations. (U.K.)

Límites de consistencia y sus implicaciones agrícolas en un suelo ultisol de sabana del estado Monagas, Venezuela

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Américo Hossne

2004-01-01

Full Text Available El conocimiento de las propiedades físicas de los suelos agrícolas y bióticos proporciona información para el manejo de equipos agrícolas, procesos de compactación y la labranza convencional y conservacionista. A medida que la humedad edáfica aumenta, genera diversos estados del suelo; e.g. una menor interacción entre partículas adyacentes y un comportamiento que se aproxima al del líquido. El inicio de la sensibilidad de compactación, parece ser el límite plástico del suelo bajo una bien definida energía de compactación. El objetivo general, de este estudio fue caracterizar sistemáticamente, con las implicaciones de ingeniería posibles, los suelos agrícolas de sabana del Estado Monagas de Venezuela. Los objetivos específicos consistieron en determinar: a- los límites de Atterberg; y b- el índice de plasticidad y friabilidad. Para ello se utilizó los procedimientos de laboratorio de Mecánica de Suelos: ASTM D427-61 para el límite de contracción, ASTM D424-59 para el límite plástico y ASTM 423-66 para el límite líquido, de un suelo de sabana en muestras aleatorias a las profundidades de 0-15, 15-30, 30-45 y 45-60 cm. Se utilizó el análisis de regresión para interpretar la proporción de la variancia entre parámetros. Los resultados indicaron valores de: límite de contracción de 4,22–5,20%, límite plástico de 12,92–14,04%, límite líquido de 16,94–19,43%, índice de plasticidad de 3,59–5,78% e índice de friabilidad de 8,63–8,84%. Se concluye que los valores concuerdan con la bibliografía y el rango de uso agrícola se encuentra entre 8% y 15% para el suelo en estudio.

Erosión y pérdida de nutrientes en diferentes sistemas agrícolas de una microcuenca en la zona periurbana de la ciudad de Puebla, México

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Rosalía Castelán Vega

2017-07-01

Full Text Available El suelo es un componente natural de gran importancia en la sostenibilidad de los ecosistemas, su degradación se debe, en la mayoría de los casos, al mal manejo bajo condiciones de ladera, lo que disminuye su productividad y su capacidad para sostener la vida humana. Se evaluó la producción de sedimentos y la pérdida de nutrientes durante el año 2013 en sistemas agrícolas representativos de la zona periurbana de la ciudad de Puebla, México; con el objetivo de ponderar el coeficiente de enriquecimiento de dichos sedimentos, y así identificar el sistema agrícola que menor perdida de fertilidad genera. Se instalaron parcelas delimitadas con dimensiones de 3 m de ancho y 9 m de largo con pendiente homogénea de 9% de inclinación, en los sistemas: maíz, maíz-calabaza y maíz-avena. Se recolectaron los sedimentos, a los cuales se les determinó la concentración de materia orgánica, nitrógeno y fósforo, según lo marca la NOM-021-SEMARNAT-2000. La producción de sedimentos y escorrentía fue significativamente mayor en el sistema agrícola de maíz (54.6 mm y 37.9 Mg ha‑1, respectivamente y menor en maíz-calabaza. Los coeficientes de enriquecimiento de los sedimentos erosionados fueron en su mayoría, superiores a la unidad, destacando la materia orgánica con los coeficientes más altos. Se observó una fuerte correlación entre la producción de sedimentos y las pérdidas de materia orgánica, nitrógeno y fósforo, en los sistemas agrícolas. Los resultados obtenidos demuestran que el actual manejo de los cultivos agrícolas en la zona de estudio, favorecen la degradación de los suelos. De igual forma, los resultados generados son una base importante para establecer estrategias agrícolas y disminuir áreas degradadas en los espacios rurales de la zona periurbana de la ciudad de Puebla, México.

Contaminación y control de las quemas agrícolas en Imperial, California, y Mexicali, Baja California

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Margarito Quintero Núñez

2008-01-01

Full Text Available La quema de residuos agrícolas en los valles de Mexicali e Imperial, separados por una línea divisoria, constituye una fuente importante de emisión de contaminantes al aire, de compuestos como el metano (CH4, monóxido de carbono (CO, bióxido de nitrógeno (NO2, hidrocarburos (NMHC y partículas menores a 10 micras (PM10. Para abordar el problema de los humos agrícolas se debe considerar la cuenca atmosférica común, formada por ambos valles, que comparten un clima extremoso cálido y seco, con menos de 80 mm anuales de lluvia, y basan su economía en la agricultura, y el de Mexicali además en la industria manufacturera y otras actividades. En Mexicali, lo que se quema es sobre todo residuos de trigo y en menor proporción de cebada, cártamo y maíz. Los daños a la salud ocasionados por las emisiones de PM10 son significativos en ambos valles

On-line application of the PANTHER advanced nodal code

International Nuclear Information System (INIS)

Hutt, P.K.; Knight, M.P.

1992-01-01

Over the last few years, Nuclear Electric has developed an integrated core performance code package for both light water reactors (LWRs) and advanced gas-cooled reactors (AGRs) that can perform a comprehensive range of calculations for fuel cycle design, safety analysis, and on-line operational support for such plants. The package consists of the following codes: WIMS for lattice physics, PANTHER whole reactor nodal flux and AGR thermal hydraulics, VIPRE for LWR thermal hydraulics, and ENIGMA for fuel performance. These codes are integrated within a UNIX-based interactive system called the Reactor Physics Workbench (RPW), which provides an interactive graphic user interface and quality assurance records/data management. The RPW can also control calculational sequences and data flows. The package has been designed to run both off-line and on-line accessing plant data through the RPW

Nuclear power: consolidation or change

International Nuclear Information System (INIS)

1986-02-01

Currently about 45% of the electricity consumed in Scotland comes from nuclear sources and when the power station at Torness, near Edinburgh, is fully commissioned it will be about 60%. Torness is an AGR type reactor and the Scottish Electricty Board (SSEB) consider that there is no case for changing to a PWR type design for any future reactor built in the UK. The economics of 'a next AGR' and a PWR reactor are compared. The construction times for the Torness programme, the electrical output, station life, load factor, fuel costs and additional support costs are also considered, and compared with costs estimated by the Central Elecricity Generating Board (CEGB) for the proposed Sizewell-B reactor. Exposure of station staff to radiation, safety, public acceptibility and development potential, impact on industry, job creation and export potential are also discussed briefly. (UK)

Development of an Alternative Corrosion Inhibitor for the Storage of Advanced Gas-Cooled Reactor Fuel

International Nuclear Information System (INIS)

Standring, P.N.; Hands, B.J.; Morgan, S.; Brooks, A.

2015-01-01

Sellafield Lt. currently stores AGR fuel in sodium hyrodxide dosed pool water to pH 11.5 to prevent susceptible AGR fuel from failing due to inter-granular attack. The exception to the above storage practice is Thorp Receipt and Storage (TR&S) where an AGR reprocessing buffer is stored in demineralised water as the expected storage durations were short term (up to 5 years). With the extended shut-down of Thorp, storage durations have increased and this has prompted a re-evaluation of the AGR storage regime in TR&S. The use of sodium hydroxide is not feasible due to a compatibility issue with aluminum components used in LWR storage furniture. The implementation process adopted by Sellafield Ltd in developing an alternative corrosion inhibitor for spent AGR fuel is outlined. The two stranded approach evaluates the impact of candidate corrosion inhibitors on fuel integrity and on plant and processes. The development studies in support of the fuel integrity strand are reported. Candidate inhibitors were first evaluated inactively in terms of their ability to arrest propagating corrosion, radiation stability, compatibility with aluminium and environmental impact. Sodium Nitrate was concluded to be the most promising inhibitor. Sodium nitrate was subsequently tested with active AGR brace material. These studies involved the use of bespoke test equipment and techniques. The studies demonstrated that propagating corrosion could be arrested using 10 ppm nitrate and showed that the resultant nitrate film required relatively high chloride concentrations to break it down over the study duration of 60 days. The development studies to date have provided the confidence that sodium nitrate has the potential to be an effective inhibitor for AGR fuel. The final phase of the fuel integrity strand involves a Lead Container Study using whole AGR pins. A staged approach is being adopted in the study programme where proceeding to a more onerous study is not progressed until positive

Análisis de redes sociales para catalizar la innovación agrícola: de los vínculos directos a la integración y radialidad

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Norman Aguilar-Gallegos

2016-07-01

Full Text Available Se analizan los efectos de las interacciones, directas e indirectas, entre agricultores y otros actores relevantes en el intercambio de información y conocimiento para la innovación agrícola. Los datos se obtuvieron al preguntar a 120 agricultores «¿de quién aprende y/o a quién recurre para obtener información o conocimiento de cuestiones técnicas y productivas en torno a su unidad de producción?». Se emplean indicadores del análisis de redes sociales para proponer lineamientos que permitan catalizar la innovación agrícola. Los resultados confirman la importancia de los vínculos indirectos, pues estos permiten que los agricultores alcancen mejor información de fuentes externas. Se recomienda que los programas encaminados a promover la innovación agrícola consideren la interacción preexistente en las redes de los agricultores.

Rehabilitación de un suelo salino con yeso agrícola en un cultivo de nogal en el Valle del Yaqui

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Alma Trasviña Barriga

2018-01-01

Full Text Available El cultivo de nogal es una actividad en amplio crecimiento en el Valle del Yaqui, Sonora. Las zonas nogaleras de la región se caracterizan por presentar problemas de salinidad y altas concentraciones de sodio intercambiable, lo que provoca disminución en la productividad de la nuez pecana. Al terminar la temporada de riego con agua del sistema de presas del Río Yaqui, el uso de agua de pozos profundos es utilizada, generalmente en los meses de mayo a agosto. Esto puede ocasionar acumulación de sales en el suelo cuando el agua es de mala calidad. El yeso agrícola ha sido utilizado como enmienda para rehabilitar el suelo mejorando las propiedades químicas del mismo. El objetivo del presente estudio fue determinar el efecto de la aplicación de yeso agrícola en un suelo salino de un huerto de nogal en el Valle del Yaqui. Se llevó a cabo la rehabilitación durante dos años, en el primer año se emplearon dosis de 5 y 10 Mg ha-1, mientras que en el segundo año 2 Mg ha-1 de yeso agrícola. Se realizaron dos lavados por melgas después de cada aplicación. Los análisis químicos del suelo se ejecutaron de acuerdo a la NOM-021-RECNAT-2000 durante tres años, previo y posterior a las aplicaciones de enmienda. Posterior a la aplicación de enmienda, disminuyeron los valores de conductividad eléctrica de 12.41 a 6.29 dS m-1, porcentaje de sodio intercambiable de 12.48 a 5.57 y relación de adsorción de sodio de 10.54 a 4.88 en la profundidad de 0-30 cm en la primera aplicación. El empleo de yeso agrícola y los lavados en el suelo salino del huerto de nogal mejoraron las propiedades químicas.

Caracterización del uso del suelo en las principales áreas agrícolas de la Gran Área Metropolitana (GAM de Costa Rica

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Sue Wei-Salas

2015-06-01

Full Text Available Con el objetivo de aportar información para el ordenamiento y la planificación del uso del suelo, mediante la caracterización de su utilización en las regiones agrícolas de la Gran Área Metropolitana (GAM, se realizó una investigación entre marzo 2008 y octubre 2009, por medio de Sistemas de Información Geográfica (SIG. En el estudio se utilizaron imágenes aéreas correspondientes al proyecto Misión Carta capturadas entre febrero y marzo del 2005, lo que permitió identificar la distribución y extensión de los principales cultivos existentes en la GAM. Para identificar estas áreas se utilizó el método del reconocimiento remoto, el cual consiste en conocer la apariencia de un determinado cultivo en imágenes aéreas que permiten ubicar todas las áreas con aspecto similar y así identificar la adecuada diferenciación entre cultivos y usos. La información geográfica fue procesada mediante el programa de cómputo ArgGIS 9.2, el cual permitió obtener un mapa base a escala 1:12.500. El ha sido previamente desarrollada por diferentes instituciones del país, lo que permitió caracterizar la actividad agrícola de la GAM. Los resultados muestran que la actividad agrícola cubre alrededor del 24% del área total de la GAM, destacándose la producción de hortalizas, café y plantas ornamentales bajo sarán. Las hortalizas tienen la mayor importancia en extensión, ya que abarca el 52% del área agrícola de la GAM, seguidas del café con 44%, mientras que la producción de ornamentales bajo sarán representa solamente cerca del 4%. Al analizar los cambios ocurridos en la actividad agrícola de la GAM en los últimos 28 años, en el caso del café el área de producción disminuyó en 3569 ha, lo cual corresponde al 17% de las 22 545 ha identificadas en 1983.

The need for high performance breeder reactors

International Nuclear Information System (INIS)

Vaughan, R.D.; Chermanne, J.

1977-01-01

It can be easily demonstrated, on the basis of realistic estimates of continued high oil costs, that an increasing portion of the growth in energy demand must be supplied by nuclear power and that this one might account for 20% of all the energy production by the end of the century. Such assumptions lead very quickly to the conclusion that the discovery, extraction and processing of the uranium will not be able to follow the demand; the bottleneck will essentially be related to the rate at which the ore can be discovered and extracted, and not to the existing quantities nor their grade. Figures as high as 150.000 T/annum and more would be quickly reached, and it is necessary to wonder already now if enough capital can be attracted to meet these requirements. There is only one solution to this problem: improve the conversion ratio of the nuclear system and quickly reach the breeding; this would lead to the reduction of the natural uranium consumption by a factor of about 50. However, this condition is not sufficient; the commercial breeder must have a breeding gain as high as possible because the Pu out-of-pile time and the Pu losses in the cycle could lead to an unacceptable doubling time for the system, if the breeding gain is too low. That is the reason why it is vital to develop high performance breeder reactors. The present paper indicates how the Gas-cooled Breeder Reactor [GBR] can meet the problems mentioned above, on the basis of recent and realistic studies. It briefly describes the present status of GBR development, from the predecessors in the gas cooled reactor line, particularly the AGR. It shows how the GBR fuel takes mostly profit from the LMFBR fuel irradiation experience. It compares the GBR performance on a consistent basis with that of the LMFBR. The GBR capital and fuel cycle costs are compared with those of thermal and fast reactors respectively. The conclusion is, based on a cost-benefit study, that the GBR must be quickly developed in order

Las actividades complementarias de las explotaciones agrícolas peruanas

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2002-01-01

Full Text Available La diversification des sources de revenu des exploitations agricoles est une question cruciale pour le bien être des populations rurales. En effet, toute utilisation supplémentaire du travail en milieu rural pour des activités autres que celles directement liées à l’exploitation agricole peut contribuer à augmenter les revenus, même modestement. Cet article montre que malgré le potentiel que représentent les activités complémentaires des exploitations agricoles tant en termes de création d’emplois que de revenus, elles sont encore un domaine peu compris de l’économie rurale. Cette faiblesse provient à la fois de l’hétérogénéité de ces activités qui est à la source de nombreuses confusions conceptuelles et des lacunes des statistiques nationales disponibles qui n’enregistrent pas ces activités de manière adéquate. En dépit de ces difficultés, cet article tente de donner un aperçu de l’importance et des caractéristiques des activités complémentaires des exploitations agricoles péruviennes. Quatre conclusions principales émergent de l’ensemble des résultats présentés : la sous-estimation indubitable de ces activités donc des revenus qui en découlent la part significative qu’occupe l’agriculture dans l’ensemble des activités complémentaires, la concentration de ces activités dans deux ou trois secteurs, la relative stabilité de leur distribution selon les secteurs dans le temps et dans l’espace, une division du travail assez marquée entre les hommes et les femmes. La diversificación de las fuentes de ingresos de las explotaciones agrícolas es un asunto crucial para el bienestar de las poblaciones rurales. De hecho, en el medio rural, todo trabajo adicional en actividades distintas a las directamente relacionadas con la explotación agrícola puede contribuir al aumento de los ingresos, aun en forma modesta. Este trabajo muestra que, pese a su potencial en términos de generación de empleos e

Agricultural Labor Demand in Chile: A Cointegration Approach Demanda por Trabajo Agrícola en Chile: Un Enfoque de Cointegración

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Rodrigo Saens N

2008-12-01

Full Text Available International evidence shows that the positive relationship between product and agricultural labor has weakened during the last 30 years, especially in emergent economies. Chilean agriculture has not been left out of this phenomenon The main purpose of this reseach was to estimate the causality relationships that govern the product, employment and salaries in the Chilean silviculture-agricultural-livestock sector, using a cointegration approach. Quarterly data from the 1996-2005 period were employed to estimate agricultural labor demand. A Cobb-Douglas agricultural production function was employed and from it were derived the minimum cost function and the labor demand as bases of this study; the latter was approximated log-linearly to find different measures of elasticity. The main results shows that the estimated demand for agricultural labor has long-run employment-product and employment-salary elasticities of 0.38 and -0.88, respectively. An important conclusion suggests that, compared with the employment-product and employment-salary elasticities of labor demand on the aggregated level, agricultural employment in the long run results less sensitive to changes in the product, but more sensitive to changes in salaries.La evidencia internacional muestra que la relación positiva entre producto y empleo agrícola se ha debilitado en los últimos 30 años, especialmente en economías emergentes. La agricultura en Chile no ha estado al margen de este fenómeno. El objetivo principal de esta investigación fue estimar las relaciones de causalidad que rigen al producto, el empleo y los salarios en el sector silvoagropecuario chileno, utilizando un enfoque de cointegración. Para la estimación de la demanda por trabajo agrícola se utilizaron datos trimestrales del período 1996 a 2005. Se utilizó una función de producción agrícola tipo Cobb-Douglas, a partir de la cual se derivó la función de costo mínimo y la demanda por trabajo base de

Fast reactor fuel pin behaviour modelling in the UK

Energy Technology Data Exchange (ETDEWEB)

Matthews, J R [UKAEA, Harwell, Didcot, Oxon (United Kingdom); Hughes, H [Springfields Nuclear Power Development Laboratories, Springfields, Salwick, Preston (United Kingdom)

1979-12-01

Two fuel behaviour codes have been applied extensively to fast reactor problems; SLEUTH developed at Sprlngfields Nuclear Laboratory and FRUMP at A.E.R.E. Harwell. The SLEUTH fuel pin endurance code was originally developed to define a programme of power cycling and power ramp experiments In Advanced Gas Cooled Reactors (AGRs) where, because of the very soft cladding, pellet clad interaction is severe. The code was required to define accelerated test conditions to generalise from the observed endurance to that under other power histories and to select for investigation the most significant design, material and operational variables. The weak clad and low coolant pressure combine to make fission gas swelling a major contributor to clad deformation while the high clad ductility renders the distribution of strain readily observable. This has led to a detailed study of strain concentrations using the SEER code. SLEUTH and SEER have subsequently been used to specify power cycling and power ramp 112 experiments in water cooled, fast and materials testing reactors with the aim of developing a unified quantitative model of pellet-clad interaction whatever the reactor system. The FRUMP fuel behaviour code was developed specifically for the interpretation of fast reactor fuel pin behaviour. Experience with earlier models was valuable In its development. Originally the model was developed to describe behaviour during normal operation, but subsequently the code has been used extensively in the field of accident studies. Much of the effort in FRUMP development has been devoted to the production of physical models of the various effects of irradiation and the temperature gradients on the structure of the fuel and clad. Each process is modelled as well as is permitted by current knowledge and the limitations of computing costs. Each sub-model has a form which reflects the underlying mechanisms, where quantities are unknown values are assigned semi-empirically, i.e. coefficients

Fast reactor fuel pin behaviour modelling in the UK

International Nuclear Information System (INIS)

Matthews, J.R.; Hughes, H.

1979-01-01

Two fuel behaviour codes have been applied extensively to fast reactor problems; SLEUTH developed at Sprlngfields Nuclear Laboratory and FRUMP at A.E.R.E. Harwell. The SLEUTH fuel pin endurance code was originally developed to define a programme of power cycling and power ramp experiments In Advanced Gas Cooled Reactors (AGRs) where, because of the very soft cladding, pellet clad interaction is severe. The code was required to define accelerated test conditions to generalise from the observed endurance to that under other power histories and to select for investigation the most significant design, material and operational variables. The weak clad and low coolant pressure combine to make fission gas swelling a major contributor to clad deformation while the high clad ductility renders the distribution of strain readily observable. This has led to a detailed study of strain concentrations using the SEER code. SLEUTH and SEER have subsequently been used to specify power cycling and power ramp 112 experiments in water cooled, fast and materials testing reactors with the aim of developing a unified quantitative model of pellet-clad interaction whatever the reactor system. The FRUMP fuel behaviour code was developed specifically for the interpretation of fast reactor fuel pin behaviour. Experience with earlier models was valuable In its development. Originally the model was developed to describe behaviour during normal operation, but subsequently the code has been used extensively in the field of accident studies. Much of the effort in FRUMP development has been devoted to the production of physical models of the various effects of irradiation and the temperature gradients on the structure of the fuel and clad. Each process is modelled as well as is permitted by current knowledge and the limitations of computing costs. Each sub-model has a form which reflects the underlying mechanisms, where quantities are unknown values are assigned semi-empirically, i.e. coefficients

Mecanización agrícola, empleo y migración en el norte de Tamaulipas

Directory of Open Access Journals (Sweden)

José Luis Contreras Valenzuela

1986-05-01

Full Text Available El objetivo del presente trabajo es analizar el modelo de desarrollo agrícola recientemente adoptado en los distritos de riego del norte de Tamaulipas, y los efectos sobre el empleo y la migración de la población rural. Dicho análisis se efectuará a partir de dos premisas fundamentales: una de ellas es la internacionalización del proceso productivo que se manifiesta con la presencia de una nueva división internacional del trabajo y lo que en este ensayo es llamada economía campesina, que fue la fuente primaria de la acumulación de capital de la agricultura mexicana, la cual jugará un papel importante para la acumulación de capital de la agricultura de los Estados Unidos de América, mediante la oferta de fuerza de trabajo agrícola barata, permitiendo el desarrollo de la agricultura comercial, modelo que ahora se ha volcado sobre la economía campesina condenándola a su desaparición como forma de subsistencia de la población rural, a quien expulsa de sus unidades de producción mediante el acaparamiento y el rentismo.

Biorremediación de un suelo agrícola impactado con aceite residual automotriz

OpenAIRE

Pasaye Anaya, Lizbeth

2011-01-01

El aceite residual automotriz (ARA) derivado del uso de automotores es una mezcla de hidrocarburos (HC) alifáticos, aromáticos y otros que en el suelo impide la actividad microbiana para el reciclaje de elementos esenciales para la vida. El objetivo de este trabajo fue analizar la biorremediación (BR) por bioestimulación (BS) de un suelo agrícola impactado con ARA. Para ello, el suelo contaminado con la mezcla de HC se biorremedió por BS con una solución mineral (SM), lombricomposta (LC) y ab...

Agricultura familiar e as rendas não-agrícolas na Região Metropolitana de Porto Alegre : um estudo de caso dos municípios de Dois Irmãos e Ivoti - RS

OpenAIRE

Marco Antonio Verardi Fialho

2000-01-01

Esta estudo discute a importância das rendas não-agrícolas na composição da renda total dos agricultores familiares de uma região fortemente marcada pela pluriatividade de seus produtores rurais. Os dados utilizados neste estudo foram obtidos a partir de uma pesquisa de campo realizada junto a 57 agricultores familiares dos municípios de Dois Irmãos e Ivoti, RS. A metodologia utilizada consistiu na identificação e quantificação das rendas agrícolas e não-agrícolas bem como na caracterização d...

Plant Measurement, Sampling and Analysis for Accountancy Purposes with Particular Reference to Separation Plants at Windscale; Mesures, Echantillonnages et Analyses en Usine a des Fins Comptables, Notamment dans les Installations de Separation de Windscale; Izmereniya, vzyatie obraztsov i analizy v tselyakh ucheta na opyte ustanovki razdeleniya radioizotopov v uindskejle; Medicion, Muestreo y Analisis para Fines Contables, Especialmente en las Plantas de Separacion de Windscale

Energy Technology Data Exchange (ETDEWEB)

Davidson, A. S.; Elliott, F.; Powell, R.; Swinburn, K. A. [United Kingdom Atomic Energy Authority, Windscale and Calder Works, Cumberland (United Kingdom)

1966-02-15

All figures for special materials accountancy purposes contain one or more of three parameters, namely plant measurement, sampling and analysis. For plant measurements it is best to use weighings wherever possible, e.g. the plutonium in the feed to the New Separation Plant is based on the weight of uranium rods fed. Methods used for measuring volumes are discussed, e.g. (a) pneumercator, and (b) tracer method using radioactive caesium. Judged accuracies and precisions of each method are given. The sampling of solutions in a batch process is done by using evacuated tubes after thorough homogenization of the solution. For ''flowing'' streams, where high accuracy is required, a continuous sampler has been devised and is used on the feed to the New Separation Plant. Drilling of metal ingots is the normal sampling method at Windscale, whereas for other solids the method is to homogenize as far as possible (e.g. a Y cone blender is used for plutonium oxide) and then sample. For the chemical analysis, the precision required of the method depends on the number of determinations in each accounting period. Thus a large number of analyses are required for an accurate but imprecise method. It may be more economical to use fewer determinations with a more precise method. Methods for determining plutonium are discussed in detail, e.g. (a) radiochemistry, (b) colorimetrically using thoronol, (c) plutonium separation, complexing with EDTA and back titration of the excess EDTA, (d) titrimetry (e) isotope dilution followed by mass spectrometry and (f) differential spectrometry. Methods for determining uranium are outlined, e.g. (a) gravimetry as U{sub 3}O{sub 8}, (b) ether extraction followed by gravimetry or colorimetry, (c) titrimetry, (d) isotope dilution followed by mass spectrometry and (e) enrichment determination by mass spectrometry or line shift emission spectrography. With all accounting methods standards are used to give quality control and to show any inaccuracy which

Determinantes dos preços de terras no Brasil: uma análise de região de fronteira agrícola e áreas tradicionais

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Aline Barrozo Ferro

2013-09-01

Full Text Available O estudo tem como objetivo analisar o impacto de variáveis sobre o preço da terra agrícola entre 2000 e 2010 em três regiões: fronteira agrícola (sul do Maranhão, sul do Piauí, leste do Tocantins e oeste da Bahia, área de transição (exploração relativamente recente, mas representa um importante produtor de soja, como o Centro-Oeste e desenvolvida (áreas tradicionais, como o Sul do País. Foram utilizadas as variáveis preço de soja, produtividade, área cultivada, crédito rural, investimento em transporte, capacidade de armazenamento e preço da terra no período anterior. A partir do modelo econométrico de dados em painel, observou-se que o preço da soja (representando a renda do produtor, teve relação estreita e positiva com o preço da terra. Verificou-se, também, que nas regiões menos ocupadas um aumento da demanda por área pode impactar negativamente em seu preço devido à maior elasticidade da oferta de terras e à possibilidade de conversão de terras brutas e de pastagens em agrícolas. Já na região desenvolvida, a relação é positiva, já que a oferta de terras é praticamente inelástica. O fator especulativo foi bastante representativo na fronteira agrícola, o que evidenciou o forte interesse de investidores no potencial de valorização da terra no período.

Verificação de requisitos de segurança de tratores agrícolas em alguns municípios do estado de São Paulo

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Ila Maria Corrêa

Full Text Available Um levantamento de informações foi realizado com o objetivo de avaliar as condições de segurança de tratores agrícolas novos e usados em alguns municípios do estado de São Paulo. Foram avaliados 487 tratores em uso em 270 propriedades agrícolas do estado de São Paulo e 31 tratores novos disponíveis em revendas e em exposição em feiras agrícolas, sendo inspecionados alguns requisitos de segurança relativos a posto de operação, acesso, comandos, proteção de partes móveis, disponibilização de avisos contra riscos de acidentes e requisitos necessários para tráfego em rodovias, previstos em documentos normativos nacionais e/ou internacionais. Verificou-se que os tratores em uso no campo não favorecem a segurança e o conforto do operador, enquanto que os tratores novos mostram tendência de atendimento aos requisitos de segurança e conforto, principalmente aqueles relacionados ao posto de operação e à proteção de partes ativas.

La combinación de sistemas agrícolas tradicionales y comerciales, el proceso de conversión en Cruz de Piedra, Estado de México

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Leonardo Ernesto Márquez Mireles

2007-01-01

Full Text Available La comprensión de las relaciones establecidas entre la cultura y la agricultura de una población dedicada al cultivo, ubicada en el ecotono, al sur del volcán Nevado de Toluca, en el Estado de México; genera varias preguntas, entre ellas: ¿Cuáles son las transformaciones que han sufrido la organización social y el trabajo agrícola que permiten combinar un sistema agrícola convencional con un sistema agrícola tradicional? La respuesta a la pregunta se deriva en dos rubros: (1 Para que los campesinos dentro del proceso de conversión tengan dinero para la compra de insumos agroindustriales, este debe ingresar a través de actividades asalariadas o de la migración; (2 La conversión implica desarrollar una agricultura de monocultivos y dejar a un lado la diversidad de cultivos de la agricultura tradicional. Los resultados que se presentan a lo largo de este artículo muestran cómo se realizó esta combinación y cuáles fueron los mecanismos de ajuste social y cultural a su ambiente y al mercado.

Fungos micorrízicos arbusculares em campos de murundus após a conversão para sistemas agrícolas no cerrado

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Paula Camylla Ramos Assis

2014-12-01

Full Text Available Os campos de murundus são fitofisionomias de ocorrência no bioma Cerrado com funções ecológicas importantes para a manutenção da sustentabilidade do solo; e a conversão para sistemas agrícolas pode provocar alterações nos atributos físicos, químicos e biológicos do solo ainda não avaliados, como a redução da biodiversidade de fungos micorrízicos arbusculares. O objetivo deste estudo foi avaliar como a conversão dos campos de murundus em áreas de sistema agrícola altera a comunidade de fungos micorrízicos arbusculares (FMAs. Os tratamentos constituíram-se de três áreas agrícolas submetidas ao mesmo manejo e uso agrícola em uma cronossequência (7, 11 e 14 anos e duas na área referência [campo de murundus, em topo (TM e entre os murundus (EM]. Os esporos de FMAs foram extraídos, contados, e as espécies de FMAs identificadas pelas características morfológicas. O total de FMAs recuperado foi de 27 espécies, sendo nove espécies da família Acaulosporaceae, uma Ambisporaceae, sete Glomeraceae, duas Claroideoglomeraceae e oito Gigasporaceae. Desse total, as espécies Acaulospora scrobiculata, Glomus macrocarpum, e Gigaspora sp. ocorreram em todas as áreas nos dois anos estudados. As espécies Acaulospora mellea, Acaulospora cavernata, Acaulospora colombiana, Glomus diaphanum, Scutellospora reticulata e Scutellospora sp. só foram encontradas nos campos de murundus. A conversão de campos de murundus em área agrícola modificou a ocorrência e composição da comunidade de FMAs; as espécies Acaulospora scrobiculata, Glomus macrocarpum, Claroideoglomus etunicatus e Gigaspora sp ocorreram em todas as áreas e a não ocorrência de algumas espécies nas áreas de cultivo, como as espécies Acaulospora cavernata, Acaulospora colombiana, Rhizophagus diaphanus, Scutellospora reticulata e Scutellospora sp. representa perda de diversidade desses fungos. Portanto, este estudo tratou-se do primeiro relato da ocorrência e da

Impactos provocados por la sequía agrícola en el cultivo de Plátano (Musa en áreas del municipio Venezuela, Ciego de Ávila, Cuba

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Yurisbel Gallardo Ballat

2017-12-01

Full Text Available En la presente investigación se realiza el análisis del impacto provocado por la sequía agrícola en el cultivo del Plátano Vianda (Musa paradisiaca en un período de 13 años en áreas de municipio de Venezuela de la provincia de Ciego de Ávila. Cuba, para el análisis de los períodos de sequía se utilizó el Índice de Sequía Agraria (ISA el cual presenta dentro de su algoritmo matemático como variables determinantes la Evapotranspiración de Referencia, que en este caso se determinó con el método de Penman Monteith FAO-1998, el déficit de humedad, la precipitación efectiva y el rendimiento agrícola. Los resultados obtenidos demuestran que los procesos de sequías agrícolas se manifiestan en todos los ciclos del cultivo, afectando de manera general los rendimientos, la evaluación de fenómeno es de gran utilidad para el manejo sostenible de ecosistemas agrarios en aras de lograr mejores resultados productivos a mediano y corto plazo. El análisis de este fenómeno climatológico desde el punto de vista agrícola, permite trazar estrategias para la aplicación de métodos de conservación del suelo y del recurso hídrico a los agricultores.

Reseña de tesis doctoral: Consolidación de cadenas globales de valor y desarrollo de clusters locales: El caso de la maquinaria agrícola en Argentina

OpenAIRE

Lan, Diana

2015-01-01

El aporte del trabajo de investigación desarrollado por Federico Langard tiene que ver con la industria de maquinaria agrícola argentina y su larga tradición originada en el desarrollo de la agricultura pampeana. Se concentra en el Este de Córdoba y el Centro-Sur de Santa Fe. Esta industria aparece por las necesidades de las formas de producción agrícola, como talleres de reparación de maquinaria importada y luego como productoras que adaptan y fabrican los productos más complejos tecnológica...

Potencial de biodegradación de DDT y sus metabolitos en suelos agrícolas de Chinandega

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Carlos E. Noguera Solís

2008-04-01

Full Text Available LA PRESENTE INVESTIGACIÓN EVALUÓ EL POTENCIAL DE BIODEGRADACIÓN DEL 1,1,1-Tricloro- 2,2-bis(4-clorofeniletano (DDT y sus metabolitos en suelos agrícolas pertenecientes a fincas del municipio de El Viejo, Chinandega, a través de dos ensayos: ensayo de biodegradación ex situ y ensayo de búsqueda e identificación de microorganismos capaces de biodegradar DDT. En el primer ensayo se determinó el porcentajede biodegradación, bajo condiciones idóneas, durante un período de 100 días en diferentes lotes de suelo con diferentes aditivos (cachaza y estiércol a través de la aplicación de cepas microbianas comerciales Environoc 201®. De ello se obtuvo como resultado un porcentaje de biodegradación mayor para el lote que no presentaba aditivos orgánicos, siendo éste de 23,92%. En el ensayo de búsqueda eidentificación de bacterias se lograron aislar e identificar cepas microbianas nativas de los suelos agrícolas objeto de estudio utilizando medios de cultivo con DDT como única fuente de carbono y energía. Como resultado se lograron identificar los siguientes microorganismos: Pseudomonas sp., Streptomyces sp., Phanerochaetechrysosporium y levaduras.

Pentose sugars inhibit metabolism and increase expression of an AgrD-type cyclic pentapeptide in Clostridium thermocellum.

Science.gov (United States)

Verbeke, Tobin J; Giannone, Richard J; Klingeman, Dawn M; Engle, Nancy L; Rydzak, Thomas; Guss, Adam M; Tschaplinski, Timothy J; Brown, Steven D; Hettich, Robert L; Elkins, James G

2017-02-23

Clostridium thermocellum could potentially be used as a microbial biocatalyst to produce renewable fuels directly from lignocellulosic biomass due to its ability to rapidly solubilize plant cell walls. While the organism readily ferments sugars derived from cellulose, pentose sugars from xylan are not metabolized. Here, we show that non-fermentable pentoses inhibit growth and end-product formation during fermentation of cellulose-derived sugars. Metabolomic experiments confirmed that xylose is transported intracellularly and reduced to the dead-end metabolite xylitol. Comparative RNA-seq analysis of xylose-inhibited cultures revealed several up-regulated genes potentially involved in pentose transport and metabolism, which were targeted for disruption. Deletion of the ATP-dependent transporter, CbpD partially alleviated xylose inhibition. A putative xylitol dehydrogenase, encoded by Clo1313_0076, was also deleted resulting in decreased total xylitol production and yield by 41% and 46%, respectively. Finally, xylose-induced inhibition corresponds with the up-regulation and biogenesis of a cyclical AgrD-type, pentapeptide. Medium supplementation with the mature cyclical pentapeptide also inhibits bacterial growth. Together, these findings provide new foundational insights needed for engineering improved pentose utilizing strains of C. thermocellum and reveal the first functional Agr-type cyclic peptide to be produced by a thermophilic member of the Firmicutes.

Requisitos ambientais e acesso a mercados: o setor de defensivos agrícolas Environmental requirements and market access: the pesticide sector

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Ricardo K.S. Fermam

2008-12-01

Full Text Available Os requisitos ambientais do comércio internacional são freqüentemente usados pelos países desenvolvidos como barreiras técnicas ao acesso a mercados pelos países em desenvolvimento. Conhecer estes requisitos é especialmente importante para o setor de defensivos agrícolas (pesticidas. Assim, este artigo busca identificar os principais requisitos ambientais relativos aos defensivos agrícolas, mostrando a importância dos mesmos para os comércio exterior dos países em desenvolvimento, especialmente o Brasil.The environmental requirements of the international trade are frequently used for the developed countries as technical barriers to the market access for the developing countries. To know these requirements is especially important for the sector of agricultural defensives (pesticides. Thus, this Article seeks to identify the main environmental requirements regards to the agricultural defensives, showing the importance of the same ones for the foreign trade of the developing countries, especially Brazil.

Efectos del tlcan sobre el empleo de mano de obra en el sector agrícola de México, 1994-2010

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Yuliana Lechuga Jardínez

2014-01-01

Full Text Available el Tratado de Libre Comercio de América del Norte se implementó en 1994 para solucionar el desempleo de mano de obra en el campo mexicano, sin embargo, actual - mente las zonas rurales del país enfrentan el mismo pro - blema. Se calcularon las fuentes de crecimiento del em - pleo de mano de obra, de 1994 a 2010, con la finalidad de determinar su impacto sobre el sector agrícola de Méxi - co. Los resultados indican que el cambio en la estructura productiva fue desfavorable para el empleo en general, no obstante, el agrícola creció en diez millones de jornadas debido a un incremento en la superficie cosechada y a un aumento en los requerimientos de mano de obra. En Sinaloa, el cambio en la estructura productiva y una ma - yor mecanización perjudicaron al empleo, a diferencia de lo ocurrido en Estado de México y Chiapas, en donde lo beneficiaron.

Contrato de maquinaria agrícola en el noroeste de la provincia de Buenos Aires

OpenAIRE

Ullua, Adrián

2017-01-01

En el presente trabajo se aborda el contrato de maquinaria agrícola, citando a diversos autores y su encuadre jurídico. Los cambios introducidos en el nuevo Código Civil y Comercial. La tipicidad de este tipo de contratos y las modalidades de cómo se desarrolla en el noroeste de la provincia de Aires. Para este último punto se ha utilizado el método de entrevistas, tanto a contratistas como productores agropecuarios, para tratar de vislumbrar, si se trata de contratos atípicos o subtipos cont...

Lucienville's Agriculture Corp. Ltda. Cooperativa Agrícola Lucienville Ltda.

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Patricia Boari

2008-01-01

Full Text Available Since the evolution of agriculture corporativism and through its memoirs and balance books the present study analyzes the development of Lucienville's Agriculture Corp. Ltda. during the historic peronism. On this stage the institution got a particular incidence on diverse economic activities of national agro (seed accumulation, its industrialization and commercialization, at the same time it strengthened its role as center of social services to the associates.A partir de la evolución del cooperativismo agrario argentino y a través de sus memorias y balances el presente estudio analiza el desenvolvimiento de la Cooperativa Agrícola Lucienville Ltda. durante el peronismo histórico. En esta etapa la institución adquiere particular incidencia en las diversas actividades económicas del agro regional (acopio de semillas, su industrialización y comercialización, al tiempo que refuerza su rol como centro de servicios sociales para los asociados.

Compostagem de lodo de esgoto para uso agrícola

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Mário Viana Paredes Filho

2011-12-01

Full Text Available Este trabalho de revisão de literatura tem o objetivo de demonstrar o potencial existente no lodo de esgoto proveniente das estações de tratamento de esgotos, para que o mesmo seja reaproveitado e utilizado como matéria orgânica fornecedora de nutrientes para o solo. O lodo de esgoto deve ser tratado antes da sua disposição final através de tratamentos biológicos que vão reduzir a carga orgânica e promover a estabilização e higienização do composto. A compostagem apresenta-se como uma técnica viável e relativamente de baixo custo, que atende aos padrões físicos, químicos e microbiológicos exigidos pela legislação pertinente. A reciclagem agrícola do lodo de esgoto torna-se uma alternativa segura para a disposição final deste resíduo.

Nuclear energy and independence

International Nuclear Information System (INIS)

Rotblat, J.

1978-01-01

The pro-nuclear lobby in the United Kingdom won its battle. The Report on the Windscale Inquiry strongly endorsed the application by British Nuclear Fuels (a company owned by the government) to set up a plant to reprocess spent oxide fuels from thermal reactors; a motion in Parliament to postpone a decision was heavily defeated. The Windscale Inquiry was an attempt to settle in a civilized manner what has been tried in other countries by demonstrations and violence. In this exercise, a High Court Judge was given the task of assessing an enormous mass of highly complex technical and medical material, as well as economic, social, and political arguments. The outcome is bitterly disappointing to the objectors, all of whose arguments were rejected. Although the question of whether Britain should embark on a fast breeder reactor program was specifically excluded from the Inquiry, it clearly had a bearing on it. A decision not to proceed with the reprocessing plant would have made a fast breeder program impossible; indeed, the Report argues that such a decision would involve throwing away large indigenous energy resources, a manifest advocacy of the fast breeder. Other arguments for the decision to go ahead with the reprocessing plant included the need to keep the nuclear industry alive, and the profit which Britain will make in processing fuels from other countries, particularly Japan. The author comments further on present UK policy, taking a dissenting view, and then comments on the paper, Nuclear Energy and the Freedom of the West, by A.D. Sakharov

PRAPRAG: software para planejamento racional de máquinas agrícolas PRAPRAG: software for rational planning of agricultural machines

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Erivelto Mercante

2010-04-01

Full Text Available O software PRAPRAG é uma ferramenta de escolha de máquinas e implementos agrícolas que apresentam o menor custo por área ou por quantidade produzida, bem como, faz o planejamento de aquisição das máquinas para a propriedade agrícola, do ponto de vista técnico e econômico. Foi utilizada a linguagem de programação Borland Delphi 3.0 e, a partir de prospectos das máquinas e implementos, criou-se um banco de dados onde o usuário pode cadastrar e modificar suas características de uso. O software mostrou-se uma ferramenta útil e uso amigável. O software proporciona maior rapidez, segurança e confiabilidade ao processo produtivo e econômico das propriedades, na seleção e aquisição de conjuntos mecanizados agrícolas, e na determinação de custos com a mão de obra utilizada.The software PRAPRAG is a tool used for choosing agricultural machines and implements that present the lowest cost per area or produced amount, as well as, to it makes the machines acquisition planning for the agricultural property, from both technical and economical points of view. It was used the programming language Borland Delphi 3.0. From the machine and implement handouts, it was created a database where the user can register and modify their characteristics of use. The software showed to be a useful and friendly tool. The software provides high speed, safety and reliability for the productive and economical process of the properties, at the selection and acquisition of agricultural systems, as well as for the determination of costs with the used labor.

Étude des matrices sol-gel en film mince par détection de molécule unique en champ large : diffusion moléculaire et agrégation photo-induite

Science.gov (United States)

Nutarelli, D.; Débarre, A.; Jaffiol, R.; Julien, C.; Richard, A.; Tchénio, P.; Chaput, F.; Boilot, J. P.

2004-11-01

La fluorescence de molécules de colorant dans des matrices sol-gel en film mince a été étudiée par détection de molécule unique. Outre les phénomènes de photo-blanchiment et de clignotement, un processus de photo-agrégation a été observé. Ce phénomène, dont la dynamique dépend de la présence d'oxygène, de l'intensité du laser d'excitation et de la température, montre l'existence de deux classes de molécules dans l'échantillon. Des molécules immobiles et d'autres qui diffusent. L'analyse de la dynamique d'agrégation permettra de dégager certaines caractéristiques du mécanisme de photo-agrégation et d'appréhender le rôle joué par la matrice sol-gel dans ce processus.

Nuclear Energy

International Nuclear Information System (INIS)

1982-11-01

A brief indication is given of the United Kingdom nuclear power programme including descriptions of the fission process, the Magnox, AGR and PWR type reactors, the recycling process, waste management and decommissioning, safety precautions, the prototype fast reactor at Dounreay, and the JET fusion experiment. (U.K.)

Fabrication of Uranium Oxycarbide Kernels for HTR Fuel

International Nuclear Information System (INIS)

Barnes, Charles; Richardson, Clay; Nagley, Scott; Hunn, John; Shaber, Eric

2010-01-01

Babcock and Wilcox (B and W) has been producing high quality uranium oxycarbide (UCO) kernels for Advanced Gas Reactor (AGR) fuel tests at the Idaho National Laboratory. In 2005, 350-(micro)m, 19.7% 235U-enriched UCO kernels were produced for the AGR-1 test fuel. Following coating of these kernels and forming the coated-particles into compacts, this fuel was irradiated in the Advanced Test Reactor (ATR) from December 2006 until November 2009. B and W produced 425-(micro)m, 14% enriched UCO kernels in 2008, and these kernels were used to produce fuel for the AGR-2 experiment that was inserted in ATR in 2010. B and W also produced 500-(micro)m, 9.6% enriched UO2 kernels for the AGR-2 experiments. Kernels of the same size and enrichment as AGR-1 were also produced for the AGR-3/4 experiment. In addition to fabricating enriched UCO and UO2 kernels, B and W has produced more than 100 kg of natural uranium UCO kernels which are being used in coating development tests. Successive lots of kernels have demonstrated consistent high quality and also allowed for fabrication process improvements. Improvements in kernel forming were made subsequent to AGR-1 kernel production. Following fabrication of AGR-2 kernels, incremental increases in sintering furnace charge size have been demonstrated. Recently small scale sintering tests using a small development furnace equipped with a residual gas analyzer (RGA) has increased understanding of how kernel sintering parameters affect sintered kernel properties. The steps taken to increase throughput and process knowledge have reduced kernel production costs. Studies have been performed of additional modifications toward the goal of increasing capacity of the current fabrication line to use for production of first core fuel for the Next Generation Nuclear Plant (NGNP) and providing a basis for the design of a full scale fuel fabrication facility.

Operator training facilities for CEGB advanced gas cooled reactors

International Nuclear Information System (INIS)

Green, J.F.; Birnie, S.

1980-01-01

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

Curvas de desempenho motor de um trator agrícola utilizando diferentes proporções de biodiesel de soja

Directory of Open Access Journals (Sweden)

Vanderson Rabelo de Paula

2015-07-01

Full Text Available A crise energética, associada ao aumento da demanda por combustíveis e à crescente preocupação com o meio ambiente, tem levado à busca por fontes alternativas de energia. Além disso, a entrada de novos equipamentos e máquinas agrícolas altamente competitivos, em termos de custo, vem despertando o interesse dos agricultores. No entanto, tais equipamentos, pela sua recente inserção no mercado, ainda não apresentam parâmetros que os remetam à confiabilidade. Nesse contexto, este estudo visou ao ensaio dinamométrico de tomada de potência (TDP de um trator agrícola da marca Green Horse, modelo 204, para obtenção de suas curvas de desempenho, utilizando como combustível misturas de óleo diesel e biodiesel de soja, nas proporções B2, B5, B20 e B100. Os resultados mostraram que o trator apresentou desempenho motor compatível com outros modelos de mesma potência utilizados no país, apresentando o melhor desempenho com o uso do combustível B5.

Evaluación de riesgos en sistemas agrícolas asociados a la utilización de plaguicidas en el Municipio de Kukra Hill, Nicaragua, Centroamérica

Directory of Open Access Journals (Sweden)

Juan Asdrúbal Flores-Pacheco

2013-06-01

Full Text Available La presente investigación pretende identificar y tipificar los riesgos humanos y ambientales asociados a la utilización de plaguicidas en las actividades agrícolas en el municipio de Kukra Hill, Región Autónoma del Atlántico Sur (RAAS, Nicaragua. Se trabajó desde la evaluación de sus concentraciones en suelos y escorrentías superficiales en áreas de uso agrícola, lo que es complementado con una investigación de las condiciones de seguridad laboral, tanto preventiva como correctiva, que los agro-aplicadores realizan en sus labores diarias. Se logró determinar que existen presencia y concentración de moléculas de plaguicida en concentraciones por debajo de los niveles de detección permisibles según valores guías canadienses de calidad de suelo de uso agrícola para la protección ambiental y salud humana. Se han incluido los testimonios de técnicos extensionistas privados y de instituciones gubernamentales. Los resultados muestran un escaso uso de protecciones personales y una importante exposición laboral y extra-laboral a pesticidas.

Monitoring and performance analysis of AGR boilers during commissioning and power raising

International Nuclear Information System (INIS)

El-Nagdy, M.; Harrison, R.M.

1984-01-01

The installed boiler plant, for two 1300 MW AGR stations, is comprehensively instrumented for boiler control, performance assessment and component monitoring to ensure the integrity and safe operation of the plant during normal and faulty operating conditions. Plant instrumentation and computer systems installed at site for vibration analysis during the engineering runs and data acquisition during the power raising stage have been described. The results, from early rig investigations and the vibration testing during the unfueled engineering runs, indicate that the behaviour of the plant within the practical range of operating conditions is free from vibration problems. Also the analysis of the steady state thermal and hydrodynamic behaviour of the boiler plant during the power raising phase confirms the methods and computer models used for the boiler design. (author)

Evolution de la perméabilité d'agrégats de sels sous contrainte liée à des circulations de fluides : dissolution, colmatage, déformation

OpenAIRE

Chen , Tao

1994-01-01

Le but de ce travail est d'étudier l'évolution de la perméabilité d'agrégats de sels sous contrainte lorsque les fluides circulant dans ces agrégats peuvent réagir avec le solide par des dissolutions et/ou des colmatages. Des essais de circulation de divers fluides à travers des échantillons de briques de sels sous contrainte ont permis de suivre l'évolution de la composition des fluides en cours d'essai. L'évolution des matériaux a été aussi caractérisée en cours d'essai (mesure de vitesse a...

Avaliação da aptidão agrícola das terras como subsídio ao assentamento de famílias rurais, utilizando sistemas de informações geográficas

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Elisângela Benedet da Silva

2010-12-01

Full Text Available Os assentamentos rurais no Brasil foram criados para responder a pressões localizadas e estão marcados pela falta de planejamento prévio de implantação e diagnóstico dos recursos naturais relativos a aptidão agrícola, distribuição das classes de relevo, hidrografia, vegetação e mecanismos de apoio. O objetivo desta pesquisa foi avaliar a aptidão agrícola das terras destinadas ao assentamento de famílias rurais do Instituto Nacional de Colonização e Reforma Agrária (INCRA, aplicando o Sistema de Avaliação da Aptidão Agrícola das Terras (SAAT associado a um Sistema de Informações Geográficas (SIG no Projeto de Assentamento Eldorado dos Carajás (PAEC, localizado no município de Lebon Régis/SC. No desenvolvimento da pesquisa, optou-se por utilizar mapas temáticos em sistemas de informações geográficas (SIG para armazenar e integrar os dados espaciais. O uso do SIG permitiu a análise e integração dos temas com significativa redução de tempo e subjetividade nos cruzamentos. O uso do método forneceu duas respostas básicas ao planejamento de uso dos recursos naturais das áreas rurais: as classes de aptidão agrícola, apontando os principais fatores limitantes e a viabilidade de melhoramento das terras no nível tecnológico B; e, quando confrontado com os mapas temáticos e os dados cadastrais do assentamento, revelou as regularidades e irregularidades no uso das terras em cada parcela imobiliária.

Cooperativa-escola nas Escolas Técnicas Agrícolas Cooperative-school at the Agricultural Technical Schools

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P.V. Marques

1993-12-01

Full Text Available A dificuldade de gerenciar recursos e proporcionar melhores condições de ensino para os estudantes são algumas das deficiência das Escolas Técnicas Agrícolas (ETAs brasileiras, problemas parcialmente superados por algumas escolas que adotaram a chamada Cooperativa-Escola. Neste trabalho, procura-se discutir alguns aspectos filosóficos referentes às ETAs e como a Cooperativa-Escola pode ajudar a solucionar seus principais problemas educativos e administrativos; um estudo de caso utilizando-se a técnica de auditoria administrativa foi desenvolvido numa ETA cuja Cooperativa-Escola é considerada um modelo de bom funcionamento e alguns procedimentos foram descritos, objetivando-se estender a prática de Cooperativa-Escola para outras escolas técnicas agrícolas brasileiras.Some of the problems with the Brazilian public Agricultural Technical School systems (ETAs are related to resource management and the need to improve teaching and learning conditions. Those deficiencies were partially corrected after setting up Cooperative-Schools that allow the ETAs to raise and to administrate funds. Administrative procedures of the ETAs and how the Cooperative-School could help solving their main educational and adminsitrative problems are discussed in this research. A case study using the management audit technique was developed in one ETA with a well known Cooperative-School. Some observed procedures are described with the intention of extending the practice of Cooperative-Schools to other Brazilian Agricultural Technical Schools.

Servicios ecosistémicos de polinización y heterogeneidad de paisajes agrícolas

OpenAIRE

Vieli, Lorena; Davis, Frank; Kendall, Bruce; Montalba, Rene

2015-01-01

El paisaje en el cual se insertan los sistemas agrícolas afecta procesos agreoecológicos a nivel predial. En este estudio se evaluó la relevancia de la diversidad de cultivos a escala de paisaje medida según el momento de floración de cada cultivo (floración temprana, media, tardía), para el servicio ecosistémico de polinización. Para esto se utilizó un modelo espacialmente explícito basado en estudios previos al cual se le incorporaron dinámicas de respuesta de los polinizadores al pulso de ...

Los trabajadores agrícolas mexicanos en los campos de California: migración, empleo y formación de clase en una agricultura intensiva

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Manuel Adrián Hernández Romero

2015-12-01

Full Text Available En este artículo se presenta una aproximación antropológica al proceso de formación de clase, motivado por el asentamiento y estabilización de la fuerza de trabajo migrante mexicana empleada en la agricultura de California. A partir de observación directa de las dinámicas productivas de una mercancía ilustrativa, las uvas para mesa, se describen las pautas de participación laboral en un contexto de capitalismo agrícola avanzado para explorar las formas de proletarización vinculadas al uso de mano de obra externa, analizando tanto los factores que propician proletarización como las condiciones que impiden que el empleo agrícola se iguale a otros sectores de la economía.

Uso de plaguicidas en un valle agrícola tecnificado en el noroeste de México

OpenAIRE

LEYVA MORALES, José Belisario; GARCÍA DE LA PARRA, Luz María; BASTIDAS BASTIDAS, Pedro de Jesús; ASTORGA RODRÍGUEZ, Jesús Efrén; BEJARANO TRUJILLO, Jorge; CRUZ HERNÁNDEZ, Alejandro; MARTÍNEZ RODRÍGUEZ, Irma Eugenia; BETANCOURT LOZANO, Miguel

2014-01-01

En el presente estudio se comparan dos procedimientos para conocer el uso de plaguicidas durante los ciclos otoño-invierno (O-I) 2011-2012 y primavera-verano (P-V) 2012 en el Valle de Culiacán, Sinaloa. A nivel nacional, este valle es una importante región agrícola tecnificada, productora de hortalizas y granos. Se analizaron las diferencias existentes en cuanto a cantidad total de ingrediente activo, según los registros del programa "Campo Limpio" y bitácoras de aplicación de varias empresas...

La disciplina Química para la formación ambiental del ingeniero agrónomo

OpenAIRE

Triana-Hernández, Bartolo M

2014-01-01

El objetivo del trabajo es crear una propuesta didáctica para propiciar la formación ambiental en los estudiantes de la carrera de Ingeniería Agrónoma, desde la disciplina Química. La metodología utilizada fue la de casos simulados con enfoque ciencia, tecnología, sociedad y ambiente (CTSA). La propuesta se implementó durante tres cursos y sus resultados contribuyeron a que los estudiantes mostraran mayor satisfacción por el estudio de la Química. Se comprobó que utilizando esta propuesta se ...

Unidades de produção agrícola controlada no semiárido para o tratamento de água cinza

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Aline Costa Ferreira

2013-10-01

Full Text Available As reservas de água doce, juntamente com as limitações de lançamento de efluentes no meio ambiente, culminam para a necessidade do uso racional dos recursos hídricos de modo a reduzir os impactos negativos da geração de efluentes. Nesse contexto, o trabalho foi realizado objetivando-se implantar e monitorar eficiência do tratamento da água, para o semiárido, de unidades de produção agrícola controladas UPAC’s utilizando as águas cinzas de uma lavanderia comunitária.  A pesquisa foi desenvolvida nas instalações da Lavanderia Pública do Distrito de Ribeira no município de Cabaceiras no Estado da Paraíba. Foram implantadas oito unidades de produção agrícola controlada e os parâmetros analisados das águas cinza coletadas dos pontos de observação das unidades foram: Condutividade Elétrica (CE, pH, e Oxigênio Dissolvido (OD.  No sistema foram plantadas duas culturas com destinação à alimentação animal as quais são a mucuna-preta (Mucuna pruriens (L. e o capim elefante (Pennisetum purpureum e uma para consumo humano, o maracujá (Passiflora sp. O tratamento das águas cinzas nas Unidades de Produção Agrícola Controladas promoveu uma diminuição da CE, pH e OD das águas oriundas da lavanderia, tornando uma alternativa viável e sustentável para o tratamento de água de lavanderias como também para produzir alimentos para fins animais e humanos.

Controle de dispositivos em estufa agrícola / Agricultural greenhouse control of devices

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Ricardo A. Bona

2008-05-01

Full Text Available Este artigo mostra a possibilidade de se coletar dados e controlar dispositivos e sensores através das portas serial e paralela de um computador, com aplicabilidade em uma estufa agrícola. Os dados coletados são: temperatura, umidade, pressão, estado da porta de acesso e das janelas. Os dispositivos controlados são: janela motorizada, exaustor, torneira e lâmpada. Um software está sendo desenvolvido para analisar, em tempo real, os dados coletados de sensores e realizar o controle dos dispositivos, tomando decisões como, por exemplo, abertura ou fechamento da janela da estufa. O software analisa, também, variáveis coletadas dos sensores e mostra resultados obtidos de forma gráfi ca

CEGB's new simulators provide a wide range of experience

International Nuclear Information System (INIS)

Madden, V.

1988-01-01

A training simulator imitating the Heysham-2 NPP operation with the AGR type reactor is briefly described. The simulator duplicates completely the operator room, which comprises two instrument benches (active and passive ones), operator control board, auxiliary facility, reactor shut-down monitor and a number of electric panels. The simulator imitates the work of reactor and associated systems both in normal and accidental conditions

El Perfil de Egreso del Ingeniero Agrónomo. Una Experiencia de Grupos de Discusión con Egresados El Perfil de Egreso del Ingeniero Agrónomo. Una Experiencia de Grupos de Discusión con Egresados

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Gabriel Córdova Duarte

2012-02-01

Full Text Available Se presenta un estudio de grupos de discusión en panel con ingenieros agrónomos de la Universidad de Guanajuato para determinar el perfil de salida de dicha licenciatura. Los egresados sugieren: mantener las prácticas en unidades agropecuarias, mejorar las habilidades de manejo de maquinaria y equipo agrícola, fortalecer el área básica agronómica, fomentar la visión empresarial, de comercialización, de calidad de procesos y productos, formular y evaluar proyectos productivos, formar líderes y emprendedores, desarrollar la creatividad, puntualidad, constancia, disciplina, relaciones humanas, profundizar la formación humanista y, formar con el ejemplo; vincular dependencia con egresados y universidades, al profesor y la investigación con empresas agropecuarias.This work presents a study of discussion groups in a panel with agronomist of the Universidad of Guanajuato to determine the bachelors degree graduate profile. The graduates suggested: to keep the practices in agricultural units, to improve the operating skills on agricultural and machinery equipment, to strengthen the basic agronomic area, to foment the management vision of commercialization, of products and of quality processes, formulate and evaluate productive projects, upbringing leaders and entrepreneurs; to develop creativity, punctuality, perseverance, discipline and humane relationship, to strengthen the humanist education and education by example; to create bonds between the school, the graduates, the universities, the teacher and the research with agricultural enterprises.

Uso de plaguicidas en cultivos agrícolas como herramienta para el monitoreo de peligros en salud

OpenAIRE

Virya Bravo Durán; Elba de la Cruz Malavassi; Gustavo Herrera Ledezma; Fernando Ramírez Muñoz

2013-01-01

Costa Rica ha incrementado el uso de plaguicidas de mayor toxicidad, debido entre otras cosas al desarrollo de plagas más resistentes y la necesidad que tienen algunos productos agrícolas de exportación de mantener su posición en el mercado internacional. El ser humano al entrar en contacto con los plaguicidas puede experimentar efectos adversos en su salud desde agudos hasta crónicos que se manifiestan en diferentes grados. Para generar indicadores de peligro en salud en algunos cultivos por...

Análisis de las metodologías de evaluación financiera, económica, social y ambiental de proyectos de inversión agrícola utilizadas en Colombia

OpenAIRE

Ramón Antonio Rosales Álvarez; Armando Malebranh Eraso Dorado; Clemencia Martínez Aldana; Román Leonardo Villarreal Ramos; Alexander Zamora Velandia; Susan Yurany Garzón Bautista; Catalina Micán Alba; Angélica Núñez Useche; Margarita Sanabria Martínez

2007-01-01

Se reporta una investigación enfocada a evaluar las metodologías utilizadas en la década de los noventa en proyectos de tipo agrícola, particularmente en los distritos de riego, identificando las fortalezas y debilidades teóricas y técnicas y operativas en los aspectos financieros, económicos, sociales y ambientales. A partir de una selección de los proyectos de mayor envergadura implementados por el sector agrícola durante el período se realiza la evaluación de las metodologías con base en u...

Investment with a risk attached

International Nuclear Information System (INIS)

Barrie, C.

1996-01-01

The commercial pressures on the United Kingdom's privatised nuclear power company, British Electric, are examined. The demand to deliver increasing dividends to shareholders raises questions about the ability of the company to ensure continuing safe operation of its seven AGR power stations and the Sizewell-B PWR. Investors expectations will require that the AGR stations be kept running at a high level of productivity and that the approval of the Nuclear Installations Inspectorate be sought for life extension plans for some of these ageing reactors. Yet the City expects a further reduction in engineering manpower on top of the 18% cuts over recent years made to improve productivity in the run up to privatisation. Past cuts have inevitably led to a reduction in the company's pool of experienced personnel, so a further concern is that outside contractors brought in in the future to make up shortfalls in manpower will not have the degree of expertise necessary adequately to maintain the safe operation of the AGR reactors whose design is unique to the United Kingdom. (UK)

Storage of thermal reactor fuels - Implications for the back end of the fuel cycle in the UK

International Nuclear Information System (INIS)

Hambley, D.

2016-01-01

Fuel from UK's Advanced Gas-Cooled Reactors (AGRs) is being reprocessed, however reprocessing will cease in 2018 and the strategy for fuel that has not been reprocessed is for it to be placed into wet storage until it can be consigned to a geological disposal facility in around 2080. Although reprocessing of LWR fuel has been undertaken in the UK, and this option is not precluded for current and future LWRs, all utilities planning to operate LWRs are intending to use At-Reactor storage pending geological disposal. This strategy will result in a substantial change in the management of spent fuel that could affect the back end of the fuel cycle for over a century. This paper presents potential fuel storage scenarios for two options: the current nuclear power replacement strategy, which will see 16 GWe of new capacity installed by 2030 and a median strategy, intended to ensure implementation of the UK's carbon reduction target, involving 48 GWe of nuclear capacity installed by 2040. The potential scale, distribution and timing of fuel storage and disposal operations have been assessed and changes to the current industrial activity are highlighted to indicate potential effects on public acceptance of back end activities. (authors)

Indicadores para estimar la sostenibilidad agrícola de la cuenca media del río Reventado, Cartago, Costa Rica

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Laura Ramírez

2008-01-01

Full Text Available El objetivo de este trabajo fue identificar indicadores para evaluar la sostenibilidad agrícola en la cuenca media del río Reventado. Se encontró una acumulación Ca, Mg y K en los terrenos y una disminución del porcentaje de saturación de acidez con los años de uso del suelo en agricultura, los suelos han mejorado su fertilidad con el tiempo por efecto antrópico. Se encontró una tendencia similar con el P disponible, cuyos niveles aumentaron en ≈2,3 mg.l-1.año-1, eventualmente podría reducirse la aplicación de este elemento, lo que haría más sostenible el sistema de producción. Los niveles de erosión, en la mayoría de las fincas, fueron moderados; el grosor del horizonte A y el P disponible disminuyeron al pasar de erosión leve, a moderada y a severa. El índice estructural y la capacidad de uso de las tierras indicaron en las Clases II y III, suelos moderadamente susceptibles a ser degradados, y en las clases mayores alta susceptibilidad a ser degradados. No se encontró diferencias significativas entre las clases de capacidad de uso de la tierra y la producción de los cultivos. La producción de papa y cebolla fue mayor en zonas con riego, donde la relación B/C mayor se encontró en Tierra Blanca, debido al manejo del sistema productivo. Los indicadores económicos y sociales evaluados fueron positivos para ambas regiones, no así los indicadores ambientales. La actividad agrícola aún se mantiene como una actividad rentable para los productores de la cuenca media del río Reventadoactividad agrícola aún se mantiene como una actividad rentable para los productores de la cuenca media del río Reventado.

Análisis conceptual del uso agrícola del suelo: Su incidencia en la sostenibilidad

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Maldané Cuello Espinosa

2013-05-01

Full Text Available El tema del desarrollo sostenible ha sido muy discutido y analizado en las últimas décadas; no obstante, aún no se ha desarrollado satisfactoriamente; se inició en el año de 1987 con el informe Brundtland denominado Nuestro futuro común, de la Comisión Mundial para el Medio Ambiente. En el informe se puntualiza y se define concretamente al desarrollo sostenible como: “Satisfacer las necesidades del presente sin comprometer la capacidad de satisfacer las futuras generaciones”. En la actualidad, casi todas las personas coinciden con tan importante definición; sin embargo, no se ha plasmado a los niveles que se requiere para deshacer los trances que se exhiben en ese sentido a escala mundial, fruto de los ambiciosos intereses particulares.  El suelo es uno de los recursos que, en condiciones ambientalmente normales, bien puede llenar las expectativas de poder llevar a la praxis tan anhelada descripción, integrando con perspectiva de sistema agrícola los tres elementos claves que la componen: el elemento social, el económico y el ambiental.  El desarrollo de los sistemas agrícolas y sus aplicaciones e implicaciones en el proceso de la sostenibilidad, trae consigo cambios considerables en términos social, económico y ambiental, que, indudablemente, contribuye a tan anhelado proceso, en el sentido de poder lograr un cambio en el entorno común, alcanzando a armonizar la naturaleza, los beneficios económicos y las necesidades de la población.

Identification of Four New agr Quorum Sensing-Interfering Cyclodepsipeptides from a Marine Photobacterium

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Louise Kjaerulff

2013-12-01

Full Text Available During our search for new natural products from the marine environment, we discovered a wide range of cyclic peptides from a marine Photobacterium, closely related to P. halotolerans. The chemical fingerprint of the bacterium showed primarily non-ribosomal peptide synthetase (NRPS-like compounds, including the known pyrrothine antibiotic holomycin and a wide range of peptides, from diketopiperazines to cyclodepsipeptides of 500–900 Da. Purification of components from the pellet fraction led to the isolation and structure elucidation of four new cyclodepsipeptides, ngercheumicin F, G, H, and I. The ngercheumicins interfered with expression of virulence genes known to be controlled by the agr quorum sensing system of Staphylococcus aureus, although to a lesser extent than the previously described solonamides from the same strain of Photobacterium.

Funciones agua rendimiento para 14 cultivos agrícolas en condiciones del sur de La Habana

OpenAIRE

González Robaina, Felicita; Herrera Puebla, Julián; López Seijas, Teresa; Cid Lazo, Greco

2013-01-01

El estudio de las funciones agua rendimiento y su uso dentro de la planificación del uso del agua es una vía importante para trazar estrategias de manejo que contribuyan al incremento en la producción agrícola. Utilizando los datos de consumo de agua, agua aplicada por riego, precipitaciones y los rendimientos obtenidos en más de 100 experimentos de campo realizados fundamentalmente en suelo Ferralítico Rojo de la zona sur de La Habana y con ayuda de herramientas de análisis de regresión en e...

AGR-1 Fuel Compact 6-3-2 Post-Irradiation Examination Results

Energy Technology Data Exchange (ETDEWEB)

Paul demkowicz; jason Harp; Scott Ploger

2012-12-01

Destructive post-irradiation examination was performed on fuel Compact 6-3-2, which was irradiated in the AGR-1 experiment to a final compact average burnup of 11.3% FIMA and a time-average, volume-average temperature of 1070°C. The analysis of this compact was focused on characterizing the extent of fission product release from the particles and examining particles to determine the condition of the kernels and coating layers. The work included deconsolidation of the compact and leach-burn-leach analysis, visual inspection and gamma counting of individual particles, measurement of fuel burnup by several methods, metallurgical preparation of selected particles, and examination of particle cross-sections with optical microscopy. A single particle with a defective SiC layer was identified during deconsolidation-leach-burn-leach analysis, which is in agreement with previous measurements showing elevated cesium in the Capsule 6 graphite fuel holder associated with this fuel compact. The fraction of the compact europium inventory released from the particles and retained in the matrix was relatively high (approximately 6E-3), indicating release from intact particle coatings. The Ag-110m inventory in individual particles exhibited a very broad distribution, with some particles retaining =80% of the predicted inventory and others retaining less than 25%. The average degree of Ag-110m retention in 60 gamma counted particles was approximately 50%. This elevated silver release is in agreement with analysis of silver on the Capsule 6 components, which indicated an average release of 38% of the Capsule 6 inventory from the fuel compacts. In spite of the relatively high degree of silver release from the particles, virtually none of the Ag-110m released was found in the compact matrix, and presumably migrated out of the compact and was deposited on the irradiation capsule components. Release of all other fission products from the particles appears to be less than a single

Sizewell 'dirty tricks'

International Nuclear Information System (INIS)

Martin, Steve.

1987-01-01

The pro-nuclear lobby is accused of dubious tactics to promote their case for the Sizewell-B reactor. These include reassessing future electricity demand which, it is claimed, could only be met by nuclear power, claiming that new power stations were needed to avoid blackouts during cold spells, and the reporting of a major design fault in the control rods of the Torness and Heysham AGR stations. The latter is felt to be related to the promotion by the South of Scotland Electricity Board of the AGR case, as opposed to the Central Electricity Generating Board's advocation of a PWR reactor design. The author argues for a series of coal-fired power stations instead, and a major energy conservation programme. (UK)

A microstructural study of dynamic crack propagation in nuclear graphites

International Nuclear Information System (INIS)

Burchell, T.D.; McEnaney, B.; Tucker, M.O.; Rose, A.P.G.

1986-01-01

This paper reports a new microstructural study of dynamic crack propagation in three nuclear graphites: (i) PGA, the moderator material in UK Magnox reactors; (ii) IMl-24, the moderator material in UK Advanced gas cooled reactors (AGR); and (iii) a pitch coke graphite, which is used in the fabrication of AGR fuel sleeves. The fracture mechanisms in nuclear graphites are initiated by microcrack formation at low stresses. Typically, microcracks form in regions of well-aligned binder or at favourably-oriented pores, where stress is concentrated. With increasing applied loads, microcracks propagate taking advantage of easy cleavage paths or linking with pores. Eventually, coalescence of such cracks and inherent porosity produces a crack of critical length for fast fracture. (orig./MM)

Torness. Keep it green

International Nuclear Information System (INIS)

Flood, M.

1979-01-01

The subject is discussed under the following headings: Torness foolishness (concerning the steps being taken towards constructing a nuclear power station at Torness Point in East Lothian, Scotland); the case against Torness (a summary); is Torness necessary (discusses the present, planned and forecast positions of electricity supply and demand in Scotland); how much will Torness cost, and who will pay; the local impact of Torness (on employment, infrastructure, amenity and future prospects); how reliable is the Advanced Gas Cooled Reactor (the choice of the AGR type reactor and discussions on the 'Hinkley Point incident' and the 'Hunterston incident'); how safe is nuclear power (discussion on AGR programme, nuclear accidents, sabotage, war, nuclear waste, plutonium, secrecy and security); public opposition to Torness; what can be done. (U.K.)

Design and performance of the helically coiled boilers of two AGR power stations in the United Kingdom

International Nuclear Information System (INIS)

El-Nagdy, M.; Papa, A.D.

1988-01-01

The Hartlepool and Heysham-I AGR stations have been commissioned and operating since 1983. The main features, of the design of the helical once-through boilers raising the steam for power generation, are outlined. The modifications to the feed inlet flow ferrules, necessary to improve the boiler performance and optimize the power output, have been described. Comparisons between the thermal and hydrodynamic performance of the boilers before and following these alterations are given. The improvements in the computer code predictions of the plant performance have also been presented. (author)

Os direitos da mulher à terra e os movimentos sociais rurais na reforma agrária brasileira

OpenAIRE

Deere,Carmen Diana

2004-01-01

Este artigo examina a evolução da reivindicação dos direitos da mulher à terra na reforma agrária brasileira sob o prisma dos três principais movimentos sociais rurais: o Movimento dos Trabalhadores Rurais Sem Terra (MST), os sindicatos rurais e o movimento autônomo de mulheres rurais. O mérito maior por levantar a questão dos direitos da mulher à terra é das mulheres dentro dos sindicatos rurais. Os direitos formais das mulheres à terra foram conseguidos na reforma constitucional de 1988, e ...

Models of bending strength for Gilsocarbon graphites irradiated in inert and oxidising environments

International Nuclear Information System (INIS)

Eason, Ernest D.; Hall, Graham N.; Marsden, Barry J.; Heys, Graham B.

2013-01-01

This paper presents the development and validation of an empirical model of fast neutron damage and radiolytic oxidation effects on bending strength for the moulded Gilsocarbon graphites used in Advanced Gas-cooled Reactors (AGRs). The inert environment model is based on evidence of essentially constant strength as fast neutron dose increases in inert environment. The model of combined irradiation and oxidation calibrates that constant along with an exponential function representing the degree of radiolytic oxidation as measured by weight loss. The change in strength with exposure was found to vary from one AGR station to another. The model was calibrated to data on material trepanned from AGR moderator bricks after varying operating times

The development of a transient neutron flux solution in the PANTHER code

International Nuclear Information System (INIS)

Hutt, P.K.; Knight, M.P.

1990-01-01

In the United Kingdom a new three-dimensional, two-group, homogeneous reactor diffusion code, PANTHER, has been developed for the analysis of pressurized water reactors (PWRs) and advanced gas-cooled reactors (AGRs). The code can perform a comprehensive range of calculations, steady state, depletion, and transient with either a finite difference or analytic nodal flux solution. The nodal solution allows the representation of within-node burnup variation and pin-power reconstruction in either steady-state or transient mode. Specific steady-state and transient thermal feedback modules are included for both PWRs and AGRs. The code is being developed to perform a complete range of reactor calculations from online operational support to fuel management and fault transient analysis. In the area of transient analysis, the code is currently being used for a number of PWR fault transient assessments, including rod ejection and steam-line break. In addition, work is proceeding to incorporate the PANTHER 3D nodal transient solution in the TRAC-P code. This paper outlines the development of the transient flux solutions within PANTHER

Measurement of the stored energy in the NRX reactor reflector graphite

Energy Technology Data Exchange (ETDEWEB)

Hilton, H. B.; Larson, E. A.G.

1959-07-15

With the co-operation of workers at Windscale and Harwell, whose assistance is hereby gratefully acknowledged, the stored energy content of the inner reflector graphite of NRX has been measured. Measurements made at three different elevations and at different positions through the reflector show that there is, at present, no danger to NRX from an accidental release of the energy. The energy stored in the reflector in 1958 is less by a factor five to ten than the stored energy as measured in 1953. It appears that there has been a continual release of stored energy since 1954 when, after the rehabilitation, the maximum power was raised to 40 MW. Additional thermocouples have been installed in the inner reflector, and future stored energy measurements are being scheduled. (author)

Economic analysis of agricultural enterprises in Turkey according to their level of success Análise econômica de empresas agrícolas na Turquia de acordo com seu nível de sucesso

Directory of Open Access Journals (Sweden)

Halil Kizilaslan

2009-04-01

Full Text Available In this study, agricultural enterprises in Turhal, Tokat were grouped based on their degree of success, their structural characteristics have been identified and their outcomes of activities discussed. The objective of the study was to determine the aspects that render successful agricultural enterprises different from other agricultural enterprises. The point to be achieved through the study is to assist agricultural enterprises with a more effective utilization of existing means in order to help them to develop. Data has been collected from 71 agricultural enterprises, which have been determined by Neyman's Method that is a stratified sampling method, via questionnaires. The Criterion of Agricultural Income Per Enterprise Land Decar has been applied for the classification of the enterprises according to their level of success. When the agricultural income was sufficiently examined in the enterprises, moderate successful and unsuccessful enterprises cannot obtain agricultural income to meet family labor force cost. Their agricultural level is quite below the sum of the family labour wage equivalent and the real interest of the equivalent capital. Therefore, the agricultural income of the examined enterprises is considered insufficient. The rate of the net product to the active capital is 3.45% in successful enterprises, 0.57% in those with moderate success, and for the unsuccessful ones, it has a negative value of -2.22%. This ratio for successful enterprises is close to 5%. Accordingly, the successful enterprises work more efficiently in comparison to the other enterprise groups.Neste estudo, empresas agrícolas de Turhal, Tokat foram agrupadas com base em seu grau de sucesso, suas características foram identificadas e seus resultados de atividades discutidos. O objetivo do estudo é determinar os aspectos que diferenciam empresas agrícolas de sucesso das demais. O ponto a ser alcançado pelo estudo é assistir as empresas agrícolas com um

Decommissioning in British Nuclear Fuels plc

International Nuclear Information System (INIS)

Colquhoun, A.

1988-01-01

Decommissioning projects at the BNFL Sellafield site have been selected taking the following into account; the need to gain experience in preparation for the decommissioning of the Magnox reactors and for the post Magnox stage; the need to develop larger scale projects; the need to be cost effective and to foster long term safety. The balance between prompt or delayed decommissioning has to consider operator dose uptake and radioactive waste management. The ten year plan for decommissioning at Sellafield is described briefly. Currently decommissioning is of the fuel pond and decanning plant, the Windscale Pile Chimneys, the coprecipitation plant and the uranium recovery plant. (author)

An atomic empire a technical history of the rise and fall of the British atomic energy programme

CERN Document Server

Hill, C N

2013-01-01

Britain was the first country to exploit atomic energy on a large scale, and at its peak in the mid-1960s, it had generated more electricity from nuclear power than the rest of the world combined.The civil atomic energy programme grew out of the military programme which produced plutonium for atomic weapons. In 1956, Calder Hall power station was opened by the Queen. The very next year, one of the early Windscale reactors caught fire and the world's first major nuclear accident occurred.The civil programme ran into further difficulty in the mid-1960s and as a consequence of procrastination in

Status of spent fuel management in the United Kingdom

International Nuclear Information System (INIS)

Dodds, R.

1996-01-01

Nuclear generating capacity in the UK is static with no units currently under construction following the completion of the Sizewell B PWR. The Government's reviews of nuclear energy policy and radioactive waste management policy have been published following a public consultation procedure, largely with an endorsement of current policies. Nuclear Electric plc (NE) and Scottish Nuclear Limited's (SNL) AGR and PWR stations are to be privatised as two subsidiaries of a holding company, and it is planned that the Magnox stations and their liabilities will be kept in the public sector, initially in a stand alone company but ultimately integrated with BNFL. Prompt reprocessing of all Magnox fuel will continue. NE and SNL have signed contracts for extensive reprocessing of AGR fuel. In addition, SNL has agreed contractual arrangements with BNFL for long term storage of its remaining overlife arisings of AGR fuel and has therefore on commercial ground opted not to dry store their fuel at the reactor site. NE have not yet made a decision on the fate of their AGR fuel not covered by existing reprocessing contracts. No option selection has taken place for PWR fuel. Following the closure of the Dounreay PFR and the withdrawal from the EFR project, the option of recycle of plutonium in fast reactors has been suspended. (author)

Educação do Campo no Brasil – a experiência da Escola Família Agrícola de Santa Cruz do Sul - EFASC

Directory of Open Access Journals (Sweden)

João Paulo Reis Costa

2016-10-01

Full Text Available Este artigo apresenta uma reflexão sobre a Educação do Campo no contexto da realidade brasileira, destacando o significado das Escolas Família Agrícola - EFAs. Com base na experiência da EFASC, referenciada na Pedagogia da Alternância, com a participação das famílias e suas comunidades, alternada com a formação escolar construída no ambiente escolar, as EFAs buscam promover a formação integral do jovem agricultor em técnico agrícola. Nesse processo educativo destaca-se a participação das famílias e instituições regionais como parceiros fundamentais para o desenvolvimento e formação dos estudantes, possibilitando a estes a permanência no campo por opção.

Estatuto da Terra: debates políticos e as disputas pela forma da reforma agrária no primeiro governo militar

Directory of Open Access Journals (Sweden)

Carmem Lúcia Gomes De Salis

2014-07-01

Full Text Available Em plena vigência da ditadura, em 30 de novembro de 1964, foi promulgado pelo governo militar de Humberto Alencar Castello Branco, o Estatuto da Terra, caracterizado enquanto um conjunto de dispositivos legais que definiam, entre outros fatores, o que era propriedade da terra no Brasil, bem como, os instrumentos necessários para se realizar a Reforma Agrária. Embora tenha sido aprovado pelo Congresso ainda no primeiro ano do governo, seu processo de elaboração e tramitação constituiu-se em um período de intensas discussões políticas acerca do alcance e da natureza que esta proposta deveria assumir.  Neste sentido, o presente artigo objetiva compreender as disputas políticas que ocorreram, mesmo sobre o regime de exceção, pela forma da Reforma Agrária. Para essa análise utilizamos, especialmente os discursos parlamentares proferidos nos meses que antecederam a aprovação da lei e as colunas publicadas na grande imprensa, pois essas fontes possibilitam refletir sobre os posicionamentos de diversos agentes envolvidos, como: políticos, associações patronais e o governo.

A Lei de Sementes brasileira e os seus impactos sobre a agrobiodiversidade e os sistemas agrícolas locais e tradicionais

Directory of Open Access Journals (Sweden)

Juliana Santilli

Full Text Available O artigo faz uma análise crítica dos impactos da Lei de Sementes brasileira (10.711/2003 sobre a biodiversidade agrícola e sobre a agricultura tradicional e local. A referida lei atende, principalmente, aos interesses e necessidades do sistema 'formal' de sementes e desconsidera o importante papel dos sistemas de sementes locais e tradicionais (chamados frequentemente de 'informais', nos quais as atividades de produção, intercâmbio, melhoramento e conservação de sementes são realizadas pelos próprios agricultores por meio de suas redes sociais e segundo as normas locais. Os sistemas 'formais' de sementes estão voltados, principalmente, para as espécies agrícolas de grande valor comercial e de ampla utilização em ambientes homogêneos. Assim, não são capazes de oferecer sementes adaptadas a usos e condições locais específicas e de atender às necessidades dos agricultores tradicionais e locais, que dispõem de poucos recursos e vivem em regiões heterogêneas, ambiental e culturalmente.

Escenarios de erosión bajo diferentes manejos agrícolas en la cuenca del lago de Zirahuén, Michoacán, México

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Manuel E. Mendoza Cantú

2009-10-01

Full Text Available La erosión hídrica, la desecación y pérdida de áreas y volúmenes de los lagos son problemas severos en las cuencas cerradas del Sistema Volcánico Transversal. Este deterioro comienza a extenderse a la cuenca del lago de Zirahuén, Michoacán, en la cual se encuentra uno de los pocos lagos mexicanos de aguas casi prístinas; por ello, es urgente plantear estudios que ofrezcan bases para un manejo sostenible de los recursos naturales que beneficie a los distintos usuarios del lago y de la cuenca. El objetivo de este trabajo fue predecir la erosión hídrica asociada a sistemas de manejo agrícola considerando tres tipos de labranza (tradicional, mínima y de conservación en la cuenca del lago de Zirahuén. La predicción se realizó aplicando la Ecuación Universal de Pérdidas de Suelo (EUPS dentro del contexto de un sistema de información geográfica. Los resultados indicaron que el uso de la labranza de conservación en las áreas agrícolas de la cuenca, reduciría las pérdidas de suelo a menos de 3 t ha-1 año-1 en toda el área agrícola de la cuenca, y probablemente se disminuiría la contaminación por arrastre de sedimentos en el lago de Zirahuén.

Country report for the UK

International Nuclear Information System (INIS)

Hesketh, Kevin

2001-01-01

Status of nuclear power generation in Britain can be summarised as follows: 7 Agr type reactors and 1 PWR, capacity 9.6 GW, and 7 Magnox reactors, capacity 2.9 GW. The fast reactors research and development programme is not sponsored by the Government, except for decommissioning work at Dounreay. Small BNFL-founded programme involves technology in fast reactor research and development in several fields: knowledge preservation, Capran-Cuadra European cooperation; Eu fifth framework activities; collaboration with Japanese research organisations

The seismic assessment of radially keyed graphite moderator cores

International Nuclear Information System (INIS)

Steer, A.G.; Payne, J.F.B.

1996-01-01

The modelling of AGR and Magnox cores has to deal with the very large number of components that make up the core, and the non-linear response due to the clearances in the keying system. This paper examines the conditions under which it is permissible to linearise the response. By comparing the results of discrete and continuum models of the core, the paper also shows that the number of components in the core is sufficiently large that the core can be approximated satisfactorily by an anisotropic solid material. The material has unusual properties, but these can be handled within the standard framework for the description of the elastic properties of an anisotropic solid. This description of the core by an equivalent solid material can readily be incorporated into finite element models of the reactor internal structure. Such models have been set up for both AGR and Magnox reactors. The models are being used to assess the seismic response of these reactors. (author). 5 refs, 6 figs

Efecto ambiental de agroquímicos y maquinaria agrícola en cultivos transgénicos y convencionales de algodón

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Giovanni Reyes

2010-07-01

Full Text Available Título en inglés: Environmental effects of agrochemicals and agricultural machinery in transgenic and conventional crops cotton Resumen La producción de alimentos se basa en el uso de diferentes tecnologías agrícolas, que pueden derivar en conflictos entre medioambiente y agricultura. Es significativo estudiar el impacto ambiental de las nuevas tecnologías aplicadas a la agricultura, la más importante de las cuales es la transgénesis. Este trabajo se realizó en la zona algodonera del municipio del Espinal, departamento del Tolima, para la cosecha de algodón del primer semestre de 2009, usando las metodologías de Brookes y Barfoot (2006 y Kovach y colaboradores (1992. Se estudió el efecto ambiental de la aplicación de agroquímicos y el uso de maquinaria agrícola en cultivos de algodón transgénico y convencional. Se recogió información mediante encuestas en veinte fincas productoras de algodón. El análisis de las encuestas se realizó de forma descriptiva, determinando diferencias de tipo cuantitativo y cualitativo para los predios que utilizan la tecnología convencional o la tecnología transgénicas (doble gen, Bt/RR, para luego realizar una correlación con el “Enviromental Index Quotient” (EIQ. No se encontraron diferencias entre el EIQ de campo de las dos tecnologías, aunque la tecnología transgénica tiene ventajas ambientales en el control de algunas plagas de lepidópteros. En relación con el uso de maquinaria agrícola, se encontró que la tecnología convencional genera menor liberación de CO2, gas de efecto invernadero. La metodología de Brookes y Barfoot puede adaptarse para estudios comparativos de tecnologías agrícolas en países tropicales. Palabras clave: algodón; cultivos transgénicos; efectos ambientales; maquinaria agrícola; emisiones CO2; EIQ. Abstract Food production is based on the use of various agricultural technologies, which can lead to conflicts between environment and agriculture. It