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Sample records for cairo wwr-s reactor

  1. Limits and conditions for continuous operation of WWR-S reactor

    International Nuclear Information System (INIS)

    Pittermann, P.; Listik, E.

    1979-02-01

    The fundamental technological and nuclear characteristics of the WWR-S reactor, safety limits and concepts of technical surveillance with particular attention to radiation safety of staff and of neighbouring population are outlined. The rules are mandatory for the reactor staff and for the users. The material is part of safety documentation for the WWR-S reactor. (author)

  2. Determination of neutron flux densities in WWR-S reactor core

    International Nuclear Information System (INIS)

    Tomasek, F.

    1989-04-01

    The method is described of determining neutron flux densities and neutron fluences using activation detectors. The basic definitions and relations for determining reaction rates, fluence and neutron flux as well as the characteristics of some reactions and of sitable activation detectors are reported. The flux densities were determined of thermal and fast neutrons and of gamma quanta in the WWR-S reactor core. The data measured in the period 1984-1987 are tabulated. Cross sections for the individual reactions were determined from spectra measurements processed using program SAND-II and cross section library ENDF-B IV. Neutron flux densities were also measured for the WWR-S reactor vertical channels. (E.J.). 10 figs., 8 tabs., 111 refs

  3. Safety report on WWR-S reactor

    International Nuclear Information System (INIS)

    Horyna, J.; Kaisler, L.; Listik, E.

    1981-04-01

    The present Safety Report of the WWR-S reactor summarizes findings obtained during the trial and partially also permanent operation of the reactor after two stages of its reconstruction implemented between 1974 and 1976. Most data are presented necessary for assessing probable risks of possible accident conditions whose consequences pose health hazards to individuals of the population, radiation personnel and the facilities themselves. Attention is devoted to the description of the locality, to components and systems, heat removal from the core, design aspects, the quality of new and old parts of the technological circuits, the systems of protection and control, the emergency core cooling system, the problems of radiation safety, and to the safety analyses of the abnormal states envisaged. The Report was compiled with regard to IAEA and CMEA recommendations concerning safe operation of research reactors and to the recommendations and binding decisions of the Czechoslovak Atomic Energy Commission. (author)

  4. The Waste Management Plan integration into Decommissioning Plan of the WWR-S research reactor from Romania

    International Nuclear Information System (INIS)

    Barariu, Gheorghe; Oprescu, Theodor; Filip, Mihaela; Sociu, Florin

    2008-01-01

    The paper presents the progress of the Radioactive Waste Management Plan which accompanies the Decommissioning Plan for research reactor WWR-S located in Magurele, Ilfov, near Bucharest, Romania. The new variant of the Decommissioning Plan was elaborated taking into account the IAEA recommendation concerning radioactive waste management. A new feasibility study for WWR-S decommissioning was also developed. The preferred safe management strategy for radioactive wastes produced by reactor decommissioning is outlined. The strategy must account for reactor decommissioning, as well as rehabilitation of the existing Radioactive Waste Treatment Plant and the upgrade of the Radioactive Waste Disposal Facility at Baita-Bihor. Furthermore, the final rehabilitation of the laboratories and reusing of cleaned reactor building is envisaged. An inventory of each type of radioactive waste is presented. The proposed waste management strategy is selected in accordance with the IAEA assistance. Environmental concerns are part of the radioactive waste management strategy. (authors)

  5. Comparison of thermal capabilities of the fuel assemblies for the WWR-M reactor

    International Nuclear Information System (INIS)

    Kirsanov, G.A.; Konoplev, K.A.; Findeisen, A.; Shishkina, Zh.A.

    1989-01-01

    On the basis of measurement results of the WWR-M2, WWR-M3 and WWR-M5 fuel element can temperature in the WWR-M reactor core their thermal capabilities are compared. The use of the WWR-M5 fuel assemblies instead of the WWR-M2 ones in the WWR-M reactor permits to increase specific heat loading by a factor of 2.7. The possibility to increase fuel can temperature up to 110 deg C is confirmed experimentally which corresponds to specific heat loading of 900 kW/l

  6. WWR-M reactor fuel elements as objects of permanent study and modernization

    International Nuclear Information System (INIS)

    Kirsanov, G.A.; Konoplev, K.A.; Poltavski, A.S.; Zakharov, A.S.

    2005-01-01

    Brief description of WWR-M5 thin-walled fuel elements and review of possible improvement of parameters for reactor type WWR-M and WWR-SM during transition from fuel elements HEU and LEU WWR-M2 to LEU WWR-M5 is presented. (author)

  7. Development of the Decommissioning Planning System for the WWR-M Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lobach, Y. [Institute for Nuclear Research, Kiev (Ukraine)

    2013-08-15

    Kiev's research reactor WWR-M is in operation for more than 50 years and its continued operation is planned. At the same time the development of a decommissioning plan is a mandatory requirement of the national legislation and it must be performed at the operational stage of nuclear installation as early as possible. Recently, the Decommissioning Programme for the WWR-M reactor has been developed. The programme covers the whole decommissioning process and represents the main guiding document during the whole decommissioning period, which determines and substantiates the principal technical and organizational activities on the preparation and implementation of the reactor decommissioning, the consequence of the decommissioning stages, the sequence of planned works and measures as well as the necessary conditions and infrastructure for the provision and safe implementation. The programme contains the basic directions of further decommissioning planning aimed on the timely preparation for the reactor decommissioning. This paper describes the status of the WWR-M reactor decommissioning planning attained by the middle of 2011. (author)

  8. The assessment of voce coefficient for WWR-c reactor

    International Nuclear Information System (INIS)

    Kochnov, O.Yu.; Rybkin, N.I.

    2006-01-01

    The air cavity effect in WWR-ts reactor core on the total reactivity is analyzed. The experimental data of void coefficient depending on the air cavity position inside the reactor core are obtained [ru

  9. Wet storage of nuclear spent fuel from nuclear research reactor WWR-S

    International Nuclear Information System (INIS)

    Dragolici, A. C; Zorliu, A.; Petran, C.; Mincu, I.

    2001-01-01

    Nuclear research reactor WWR-S of IFIN-HH was commissioned on 29 July 1957 and shut down on December 1997. Now it is in Conservation State. During 40 years , the reactor was operated about 150,000 hours at variable power level ranging within 5 W and 3500 kW, and producing a total power of 9,510 MWday. After 20 years of operation a large number of spent fuel elements became available for storage exceeding the stocking capacity of the small cooling pond near reactor. Therefore, in 1980 the nuclear spent fuel repository was commissioned that contains at present all the fuel elements burnt in the reactor during years, minus 51 S-36 fuel assemblies which are conserved in the cooling pond. This repository contains 4 identical ponds, each of them having the storage capacity of 60 fuel assemblies. Every pond having the outer sizes of 2,750 mm (length) x 900 mm (breadth) x 5,700 mm (depth), is made from a special aluminum alloy (AlMg 3 ), with the walls thickness of 10 mm and bottom thickness of 15 mm. Pond's lids are made of cast iron having the thickness of 500 mm; they provide only the biological protection for the maintenance personnel. A 1.5 m concrete layer ensures the biological protection of the ponds. Over the fuel elements in every pond a 4.5 m water layer is provided, playing the role of biological protection and coolant. Inside the ponds exists an aluminum rack, which contains 60 locations for fuel storage. The spacing between these locations was determined from considerations of criticality and it is was the same with that of the cooling pond near the reactor. To have supplementary protection in the case of an accident which can destroy the entire rack and put together all the fuel elements thus forming critical mass, cadmium plates were placed on the ponds bottom for a better neutron absorption. Exploitation of cooling pond near the WWR-S reactor which has the identical structure with that of nuclear spent fuel repository, demonstrate the reliability and

  10. A neutronic feasibility study for LEU conversion of the WWR-M reactor at Gatchina

    International Nuclear Information System (INIS)

    Petrov, Yu. V.; Erykalov, A.N.; Onegin, M.S.

    2000-01-01

    In this report we present the results of computations of the full scale reactor core with HEU (90%), MEU (36%) and LEU (19.75%) fuel. The reactor computer model for the MCU RFFI Monte Carlo code includes all peculiarities of the core. Calculations show that a uranium density of 3.3gU/cm 3 of MEU (36%) fuel and 8/25gU/cm 3 of LEU (19.75%) in WWR-M5 fuel assembly (FA) geometry is required to match the fuel cycle length of the HEU (90%) case with the same end of cycle (EOEC) excess reactivity. For the equilibrium fuel cycle the fuel burnup and poisoning, the fast and thermal neutron fluxes, the reactivity worth of control rods were calculated for the reference case with HEU (90%) FA and for the MEU and LEU FA. The relative accuracy of this neutronic feasibility study of fuel enrichment reduction of the WWR-M reactor in Gatchina is sufficient to start the fabrication feasibility study of MEU (36%) WWR-M5 fuel assemblies. At the present stage of technology it seems hardly possible to manufacture LEU (19.75%) fuel elements in WWR-M5 geometry due to too high uranium density. Only a future R and D can solve the problem. (author)

  11. Course of pin fuel test In WWR-M reactor core

    International Nuclear Information System (INIS)

    Zakharov, A.S.; Kirsanov, G.A.; Konoplev, K.A.

    2005-01-01

    Pin type fuel element (FE) of square form with twisted ribs was developed in VNIINM as an alternative for tube type FE of research reactors. Two variants of full-scale fuel assemblies (FA) are under test in the core of PNPI WWR-M reactor. One FA contains FE with UO 2 LEU and other - UMo LEU. Both types of FE have an aluminum matrix. Results of the first stages of the test are presented. (author)

  12. Design and experience of HEU and LEU fuel for WWR-M reactor

    International Nuclear Information System (INIS)

    Enin, A.A.; Erykalov, A.N.; Zakharov, A.S.; Zvezdkin, V.S.; Kirsanov, G.A.; Konoplev, K.A.; L'vov, V.S.; Petroc, Y.V.; Saikov, Y.P.

    1997-01-01

    A research reactor for providing high neutron fluxes has to have a compact, well breeding core with high specific heat removal. The WWR-M fuel elements meet these demands. They have optimum metal-to-water ratio and the recordly developed specific heat-transfer surface providing in a pool-type reactor at atmospheric pressure the unit heat of (900±100) kW. (author)

  13. LEU WWR-M2 fuel assemblies burnable test

    International Nuclear Information System (INIS)

    Kirsanov, G.A.; Konoplev, K.A.; Pikulik, R.G.; Sajkov, Yu. P.; Tchmshkyan, D.V.; Tedoradze, L.V.; Zakharov, A.S.

    2000-01-01

    The results of in-pile irradiation tests of LEU WWR-M2 fuel assemblies with reduced enrichment of fuel are submitted in the report. The tests are made according to the Russian Program on Reduced Enrichment for Research and Test Reactors (RERTR). United States Department of Energy and the Ministry of Atomic Energy of Russian Federation jointly fund this Program. The irradiation tests of 5 WWR-M2 experimental assemblies are carried out at WWR-M reactor of the Petersburg Nuclear Physics Institute (PNPI). The information on assembly design and technique of irradiation tests is presented. In the irradiation tests the integrity of fuel assemblies is periodically measured. The report presents the data for the integrity maintained during the burnup of 5 fuel assemblies up to 45%. These results demonstrate the high reliability of the experimental fuel assemblies within the guaranteed burnup limits specified by the manufacturer. The tests are still in progress; it is planned to test and analyze the change in integrity for burnup of up to 70% - 75% or more. LEU WWR-M2 fuel assemblies are to be offered for export by their Novosibirsk manufacturer. Currently, HEU WWR-M2 fuel assemblies are used in Hungary, Ukraine and Vietnam. LEU WWR-M2 fuel assemblies were designed as a possible replacement for the HEU WWR-M2 fuel assemblies in those countries, but their use can be extended to other research reactors. (author)

  14. Possibility for dry storage of the WWR-K reactor spent fuel

    International Nuclear Information System (INIS)

    Arinkin, F.M.; Belyakova, E.A.; Gizatulin, Sh.Kh.; Khromushin, I.V.; Koltochik, S.N.; Maltseva, R.M.; Medvedeva, Z.V.; Petukhov, V.K.; Soloviev, Yu.A.; Zhotabaev, Zh.R.

    2000-01-01

    This work is devoted to development of the way for dry storage of spent fuel of the WWR-K reactor. Residual energy release in spent fuel element assembly was determined via fortune combination of calculations and experiments. The depth of fission product occurrence relative to the fuel element shroud surface was found experimentally. The time of fission product release to the fuel element shroud surface was estimated. (author)

  15. Irradiation Performance of HTGR Fuel in WWR-K Research Reactor

    International Nuclear Information System (INIS)

    Ueta, Shohei; Sakaba, Nariaki; Shaimerdenov, Asset; Gizatulin, Shamil; Chekushina, Lyudmila; Chakrov, Petr; Honda, Masaki; Takahashi, Masashi; Kitagawa, Kenichi

    2014-01-01

    A capsule irradiation test with the high temperature gas-cooled reactor (HTGR) fuel is being carried out using WWR-K research reactor in the Institute of Nuclear Physics of the Republic of Kazakhstan (INP) to attain 100 GWd/t-U of burnup under normal operating condition of a practical small-sized HTGR. This is the first HTGR fuel irradiation test for INP in Kazakhstan collaborated with Japan Atomic Energy Agency (JAEA) in frame of International Science and Technology Center (ISTC) project. In the test, TRISO coated fuel particle with low-enriched UO_2 (less than 10 % of "2"3"5U) is used, which was newly designed by JAEA to extend burnup up to 100 GWd/t-U comparing with that of the HTTR (33 GWd/t-U). Both TRISO and fuel compact as the irradiation test specimen were fabricated in basis of the HTTR fuel technology by Nuclear Fuel Industries, Ltd. in Japan. A helium-gas-swept capsule and a swept-gas sampling device installed in WWR-K were designed and constructed by INP. The irradiation test has been started in October 2012 and will be completed up to the end of February 2015. The irradiation test is in the progress up to 69 GWd/t of burnup, and integrity of new TRISO fuel has been confirmed. In addition, as predicted by the fuel design, fission gas release was observed due to additional failure of as-fabricated SiC-defective fuel. (author)

  16. Neutronics substantiation of possibility for conversion of the WWR-K reactor core to operation with low-enriched fuel

    International Nuclear Information System (INIS)

    Arinkin, F.M.; Gizatulin, Sh.H.; Zhantikin, T.M.; Koltochnik, S.N.; Takibaev, A.Zh.; Talanov, S.V.; Chakrov, P.V.; Chekushina, L.V.

    2002-01-01

    The studies are aimed to calculation and experimental justification of possibility for conversion of the WWR-R reactor core to low-enriched nuclear fuel (the 19.75-% enrichment in isotope U-235), resulting in reducing the risk of non-sanctioned proliferation of nuclear materials which can be used as weapons materials. The analysis of available published data, related to problem of reduction of enrichment in the fuel used in research thermal reactors, has been carried out. Basing on the analysis results, reference fuel compositions have been chosen, in particular, uranium dioxide (UO 2 ) in aluminum master form and the UA1 4 alloy. Preliminary calculations have shown that, with the WWR-K reactor core preserved existing critical characteristics (the fuel composition: UA1 4 ), the uranium concentration in the fuel element is to be increased by a factor of 2.0-2.2, being impossible technologically. The calculations have been performed by means of the Monte Carlo computational codes. The program of optimal conversion of the WWR-K reactor core to low-enriched fuel has been developed, including: development of calculation models of the reactor core, composed of various designs of fuel elements and fuel assemblies (FA), on a base of corresponding computational codes (diffusion, statistical, etc.); implementation of experiments in the zero-power reactor (critical assembly) with the WWR-C-type FA, in view of correction of the computational constants used in calculations; implementation of reactor core neutronics calculations, in view of selection of the U-235 optimal content in the low-enriched fuel elements and choice of FA reload strategy at the regime of reactor core after burning; determination of the fuel element specification; determination of the critical and operational loads for the reactor core composed of rod/tubular fuel elements; calculation of the efficiency of the protection control system effectors, optimization of its composition, number and locations in the

  17. Experimental studies of spent fuel burn-up in WWR-SM reactor

    Energy Technology Data Exchange (ETDEWEB)

    Alikulov, Sh. A.; Baytelesov, S.A.; Boltaboev, A.F.; Kungurov, F.R. [Institute of Nuclear Physics, Ulughbek township, 100214, Tashkent (Uzbekistan); Menlove, H.O.; O’Connor, W. [Los Alamos National Laboratory, P.O. Box 1663, Los Alamos, NM 87545 (United States); Osmanov, B.S., E-mail: bari_osmanov@yahoo.com [Research Institute of Applied Physics, Vuzgorodok, 100174 Tashkent (Uzbekistan); Salikhbaev, U.S. [Institute of Nuclear Physics, Ulughbek township, 100214, Tashkent (Uzbekistan)

    2014-10-01

    Highlights: • Uranium burn-up measurement from {sup 137}Cs activity in spent reactor fuel. • Comparison to reference sample with known burn-up value (ratio method). • Cross-check of the approach with neutron-based measurement technique. - Abstract: The article reports the results of {sup 235}U burn-up measurements using {sup 137}Cs activity technique for 12 nuclear fuel assemblies of WWR-SM research reactor after 3-year cooling time. The discrepancy between the measured and the calculated burn-up values was about 3%. To increase the reliability of the data and for cross-check purposes, neutron measurement approach was also used. Average discrepancy between two methods was around 12%.

  18. Status and future of the WWR-M research reactor in Kiev

    Energy Technology Data Exchange (ETDEWEB)

    Bazavov, D.A.; Gavrilyuk, V.I.; Kirischuk, V.I.; Kochetkov, V.V.; Lysenko, M.V.; Makarovskiy, V.N.; Scherbachenko, A.M.; Shevel, V.N.; Slisenko, V.I. [Institute for Nuclear Research, Kiev (Ukraine)

    2001-07-01

    Kiev WWR-M Research Reactor, operated at maximum power of 10 MW, was put into operation in 1960 and during its 40-years history has been used to perform numerous studies in different areas of science and technology. Due to a number of technical problems the Research Reactor, the only one in Ukraine, was shut down in 1993 and then put into operation in 1999 again. Now there is an intention to reconstruct Kiev Research Reactor. The upgraded Research Reactor would allow solving such problems as the safe operation of Ukrainian NPPs, radioisotope production and, naturally, fundamental and applied research. The main problem for the successful operation of Kiev Research Reactor is the management and storage of spent fuel at the site, since after core unloading the spent fuel storage appears to be practically completed. So it is absolutely necessary to ship the most part of the spent fuel for reprocessing and as soon as possible. Besides, there is a need to build up the new spent fuel storage, because the tank of available storage requires careful inspection for corrosion. (author)

  19. Future of neutron-physical research at WWR-K reactor

    International Nuclear Information System (INIS)

    Akhmetov, E. Z.; Ibraev, B.M.

    1999-01-01

    Very cold neutrons (E nm) mostly indicate wave properties in the course of going through substance. The properties are determined by the value of the relation of neutron wave length to structure dimensions of the object studied. Very cold neutrons usage in nuclear-physical and neutron-optical research, in studying of structure and phase transformation of substances in different aggregative states continues to increase and very cold neutrons scattering method can be applied in those situation when other methods don't help to obtain the result (for example identification of light nuclei by roentgen rays etc.). Currently, we suppose that very cold neutrons can be applied in the course of studying superconductors, biological objects, different polymer systems and liquid crystals. Also it can be applied in radioecology - in determination of trans-uranium and trans-plutonium elements content in soil of territories where underground nuclear explosions were performed. These researches can be implemented at the WWR-K reactor. Its parameters and structure allow creating of 'Time-of-flight spectrometer very cold neutrons and cold neutrons', that functionally consists of the following basic blocks: - neutron conductor of stainless steel gage 50 mm, 8 m length; - switch block; - measurement cryostat chamber; - Vacuum shutters; - Measurement calculation complex. Earlier at the WWR-K the authors obtained maximum fluxes of ultra-cold neutrons (E=10 -7 eV) from vapor-hydrogen moderator at the temperature of 80 K and determined interaction cross-sections of ultra-cold neutrons with gas medium

  20. Application of non-destructive testing and in-service inspections to research reactors and preparation of ISI programme and manual for WWR-C research reactors

    International Nuclear Information System (INIS)

    Khattab, M.

    1996-01-01

    The present report gives a review on the results of application of non-destructive testing and in-service inspections to WWR-C reactors in different countries. The major problems related to reactor safety and the procedure of inspection techniques are investigated to collect the experience gained from this type of reactors. Exchangeable experience in solving common problems in similar reactors play an important role in the effectiveness of their rehabilitation programmes. 9 figs., 4 tabs

  1. About neutron capture therapy method development at WWR-SM reactor in institute of Nuclear Physics of Uzbekistan Academy of Sciences

    International Nuclear Information System (INIS)

    Abdullaeva, G.A.; Baytelesov, S.A.; Dosimbaev, A.A.; Koblik, Yu.N.; Gritsay, O.O.

    2006-01-01

    Full text: Neutron capture therapy (NCT) is developing method of swellings treatment, on which specialists set one's serious hopes, as at its realization the practical possibilities of the effect on any swellings open. The essence of method is simple and lies in the fact that to the swelling enter preparation containing boron or gadolinium, which one have a large capture cross-section of the thermal and slow neutrons. Then the swelling is irradiated once with the slow (epithermal) neutron beam with fluency about 10 9 neutrons /sm 2 s for a short time and single. As a result of thermal neutrons capture by the boron (or gadolinium) nuclei secondary radiation which affecting swelling cells is emitted. NCT of oncologic diseases makes the specific demands to physical parameters of neutron beams. Now research reactors are often used for NCT. However, research reactor WWR-SM (INP, Uzbekistan AS, Tashkent) doesn't provide with the epithermal neutron beams and to develop this technique the reactor, first of all, needs for obtaining the epithermal neutron beams with energy spectrum in range from 1 eV up to 10 keV and with intensity ∼ 10 9 neutron /sm 2 s. Practically it is connected with upgrade of at least one of existed reactor channels, namely with equipping with the special equipment (filters), forming from the reactor spectrum the beam of necessary energy neutrons. It requires realization of preliminary model calculations, including calculations of capture cross-sections, of filters types and their geometrical parameters on the basis of optimal selected materials. Such calculations, as a rule, are carried out on the basis of Monte-Carlo method and designed software for calculation of nuclear reactor physical and technical characteristics [1]. In this work the calculation results of devices variants and problems discussion, related with possibility of WWR-SM reactor using for NCT are presented. (author)

  2. Production of the sealed gamma-radiation sources of with iridium-192 radionuclide at the WWR-K research reactor

    International Nuclear Information System (INIS)

    Petukhov, V.K.; Chernayev, V.P.; Chabeyev, N.T.; Ermakov, E.L.; Chakrov, P.V.

    2005-01-01

    Full text: Conversion orientation of the WWR-K research reactor activity was established after renewal of its operation in 1997. A priority in reactor works was determined in the decision of tasks of practical use of nuclear technologies in a national economy in the next directions: in an industry, public health services and agriculture. The items of prime tasks: development and introduction of radiation technologies and manufacturing of radioisotopes for industry. This task included both scientific and technical program in the list of works of the Republican goals. At the WWR-K reactor within the framework of the this task solution the works on pilot production of the sealed sources of radioactive radiations (SSRR) with Ir-192 radionuclide for an industry of Republic of Kazakhstan were made. Organizational questions related to the Kazakhstan authority body and the regulating documentation were solved the first of all. The second stage was the development of the techniques of creating of devices providing an samples irradiation in reactor, control of sources sealing, measurements of the equivalent radiation doze from sources and high-quality support of SSRR manufacture over all technological way. At the third stage was made a little quantity SSRR with Ir-192 radionuclide, such as GIID-A1 (G6), for 'TEKOPS-660' Gammaray Projectors. This work served as experimental check of the decisions correctness, and has allowed to remove those lacks, to find out which it was possible only during direct manufacturing of radioactive sources. During performance of all these works the following was carried out: development and release of the documents and specifications regulating work on SSRR manufacture at the Institute of Nuclear Physics; personnel preparation and certification; preparation and equipment providing of reactor hot chambers by additional devices for work with irradiated iridium samples; development and manufacturing of the devices for iridium samples irradiation in

  3. Some aspects related to radioprotection during decommissioning of the WWR-S research reactor

    International Nuclear Information System (INIS)

    Pantazi, Doina; Stan, Camelia

    2007-01-01

    Radiological safety management ensures protection of personnel, public and environment. During decommissioning of a WWR-S type research reactor, besides other specific industrial problems, radiation and/or contamination sources will be produced and their effects have to be kept under control. In any decommissioning operation that implies working in a radioactive environment, the main concern being the minimization of the total dose received by the workers. To minimize the possible dose that an individual could receive, prior entering the working area, a definite set of stages of a radiation protection plan, developed according to ALARA principle, should be implemented. Of major interest is estimation the effective dose which operators will receive during a year, considering all operations in that he is involved and all the different possible paths of irradiation or contamination (inhalation, skin penetration, injury, etc.). The estimation of doses received by operating personnel will take into consideration the following steps: - the determination of jobs and events which could involve a significant radiation dose exposure; - whole body and extremities exposure doses should be assessed taking into consideration that the likelihood of contact with radiation and/or contamination sources is higher for hands and legs; - all possible paths of exposure will be identified (external irradiation is the most expected while the internal exposure due to intake could happen following an accidental inhalation of radionuclides or an injury in contaminated medium); - technological controls and administrative measures for exposure minimization will be rigorously implemented; - estimated doses will be compared with maximum permissible levels. The paper describes some general methodologies for computing the total effective doses received by workers involved in decommissioning operations, as well as their application for few special situations, that could contribute significantly to

  4. Study of the WWR-S IFIN-HH reactor main components stare, after 40 years working, using nondestructive methods

    International Nuclear Information System (INIS)

    Dragolici, A. C.; Zorliu, A.; Ripeanu, R.; Petran, C.; Mincu, I.

    2000-01-01

    The main goal of these investigations was to establish the security level after 40 years of working of the WWR-S research reactor of Horia Hulubei National Institute of Research and Development for Physics and Nuclear Engineering, Bucharest-Magurele. The purpose of these investigations was: checking the functionality and the physical integrity of the main components of the reactor. The physical integrity of the components is usually affected by slow processes, such as: corrosion, erosion, aging, deformations and initially hidden flaws with very slow evolutions. The methods used to determine the effects of these processes and to infer conclusions about the physical integrity of the facility are: visualizations by optical means (endoscopy and video camera), examination using ultrasounds and gammagraphy. The objective of the endoscopic checking was the view of the state of interior surfaces of the tubes and pipes, specially the inaccessible areas of the non-dismantling parts of the reactor. Big size components, such as reactor vessel, the biologic protection vessel and the main large diameter pipes of the primary cooling system, were investigated using a special device that contains a video camera connected to a PC. To obtain more information regarding the evolution of the corrosion spots, scratches and harmed areas on the investigated surfaces, their depth was checked by ultrasounds, and the welding seams structure was determined by gammagraphy. A table is given with some significant results obtained from ultrasound measurements in different points of reactor vessel, thermal column, horizontal tubes, etc. After these tests, the conclusions are: the maximum corrosion depth is 0.2 mm; - scratches are superficially, not exceeding 0.2-0.5 mm; - the traces of harmed areas are produced by the electromagnetic device utilization used for manipulation of aluminium capsules which contain irradiated substances. They are superficial, with maximum area of about 1 cm 2 ; the

  5. Accuracy of WWR-M criticality calculations with code MCU-RFFI

    International Nuclear Information System (INIS)

    Petrov, Yu.V.; Erykalov, A.N.; Onegin, M.S.

    1999-01-01

    The scattering and deviation of fuel element parameters by manufacturing, approximations of the reactor structure in the computer model, the partly inadequate neutron cross sections in the computer codes etc. lead to a discrepancy between the reactivity computations and data. We have compared reactivity calculations using the MCU-RRFI Monte Carlo code of critical assemblies containing WWR-M2 (36 enriched) an WWR-M5 (90%) fuel elements with benchmark experiments. The agreement was about Δρ≅±0.3%. A strong influence of the water ratio on reactivity was shown and a significant heterogeneous effect was found. We have also investigated, by full scale reactor calculations for the RETR program, the contribution to the reactivity of the main reactor structure elements: beryllium reflector, experimental channels irradiation devices inside the core, etc. Calculations show the importance of a more thorough study of the contributions of products of the (n, α) reaction in the Be reflector to the reactivity. Ways of improving the accuracy of the calculations are discussed. (author)

  6. Accuracy of WWR-M criticality calculations with code MCU-RFFI

    Energy Technology Data Exchange (ETDEWEB)

    Petrov, Yu V [Petersburg Nuclear Physics Institute RAS, 188350 Gatchina, St. Petersburg (Russian Federation); Erykalov, A N; Onegin, M S [Petersburg Nuclear Physics Institute RAS, 188350 Gatchina, St. Petersburg (Russian Federation)

    1999-10-01

    The scattering and deviation of fuel element parameters by manufacturing, approximations of the reactor structure in the computer model, the partly inadequate neutron cross sections in the computer codes etc. lead to a discrepancy between the reactivity computations and data. We have compared reactivity calculations using the MCU-RRFI Monte Carlo code of critical assemblies containing WWR-M2 (36 enriched) an WWR-M5 (90%) fuel elements with benchmark experiments. The agreement was about {delta}{rho}{approx_equal}{+-}0.3%. A strong influence of the water ratio on reactivity was shown and a significant heterogeneous effect was found. We have also investigated, by full scale reactor calculations for the RETR program, the contribution to the reactivity of the main reactor structure elements: beryllium reflector, experimental channels irradiation devices inside the core, etc. Calculations show the importance of a more thorough study of the contributions of products of the (n, {alpha}) reaction in the Be reflector to the reactivity. Ways of improving the accuracy of the calculations are discussed. (author)

  7. Power reactor noise measurements in Hungary

    International Nuclear Information System (INIS)

    Pallagi, D.; Horanyi, S.; Hargitai, T.

    1975-01-01

    An outline is given of the history of reactor noise research in Hungary. A brief description is given of studies in the WWR-SM reactor, a modified version of the original WWR-S thermal reactor, for the detection of in-core simulated boiling by analysis of the noise of out-of-core ionization chambers. Coolant velocity measurements by transit time analysis of temperature fluctuations are described. (U.K.)

  8. Seismic safety review mission Almaty WWR 10 MW research reactor Almaty, Kazakhstan. Final report

    International Nuclear Information System (INIS)

    Gurpinar, A.; Slemmons, D.B.; David, M.; Masopust, R.

    1995-06-01

    On the request of the government of Kazakhstan and within the scope of the TC project KAZ/0/004, a seismic safety review mission was conducted in Almaty, 8-19 May 1995 for the WWR 10 Mw research reactor. This review followed the fact finding mission which visited Almaty in November 1993 together with an INSARR mission. At that time some information regarding the seismotectonic setting of the site as well as the seismic capacity of the facility was obtained. This document presents the results of further work carried out on both the issues. It discusses technical session findings on geology, seismology, structures and equipments. In the end conclusions and recommendations of the mission are given. 4 refs, figs, tabs, 18 photos

  9. Seismic examination for assessment of safety of location of atomic energy objects (by the example of the WWR-K reactor, Ala-Tau village)

    International Nuclear Information System (INIS)

    Belyashova, N.N.

    2001-01-01

    In the Republic of Kazakhstan there are 3 research reactors (the fourth one is temporarily stopped). One of the reactors in 1998 (WWR-K, situated in the Ala Tau village, nearby Almaty city) was conserved because of a number of reasons. Including the reason of the earth crust geological structure insufficient study for the ensuring the seismic safety of the reactor site location. In 1994-1996 a number of geological-geophysical studies was carried out by Kazakhstan specialists confirming the the geological-geophysical conditions in the reactor site location in view of its safety. These condition are meeting to IAEA requirements and up-to-date standards acting in Kazakhstan

  10. Experiment on search for neutron-antineutron oscillations using a projected UCN source at the WWR-M reactor

    Science.gov (United States)

    Fomin, A. K.; Serebrov, A. P.; Zherebtsov, O. M.; Leonova, E. N.; Chaikovskii, M. E.

    2017-01-01

    We propose an experiment on search for neutron-antineutron oscillations based on the storage of ultracold neutrons (UCN) in a material trap. The sensitivity of the experiment mostly depends on the trap size and the amount of UCN in it. In Petersburg Nuclear Physics Institute (PNPI) a high-intensity UCN source is projected at the WWR-M reactor, which must provide UCN density 2-3 orders of magnitude higher than existing sources. The results of simulations of the designed experimental scheme show that the sensitivity can be increased by ˜ 10-40 times compared to sensitivity of previous experiment depending on the model of neutron reflection from walls.

  11. Decommissioning of the research nuclear reactor WWR-S Magurele - Bucharest. General presentation of the project

    International Nuclear Information System (INIS)

    Dragulescu, Emilian; Dragusin, Mitica; Popa, Victor; Boicu, Alin; Tuca, Carmen; Iorga, Ioan; Vrabie, Ionut; Mustata, Carmen

    2003-01-01

    A decommissioning project was worked out concerning the nuclear facility research reactor WWR-S Magurele-Bucharest to remove the radioactive and hazardous materials and so to exclude any risk for human health and environment. The project involves the four phases named assessment, development, operations and closeout. There are two major parts to the assesment phase: preliminary characterisation and the review and decision-making process. Characterisation is needed to develop project baseline data, which should include sufficient chemical, physical, and radiological characterisation to meet planning needs. Based on the conclusions of these studies, possible decommissioning alternative will be analyzed and: the best alternative chosen, final goal identified, risk assessments are evaluated. Also, taken into account are: regulations supporting assessment, land use considerations, financial concerns, disposal availability, public involvement, technology developments. After a decommissioning alternative was chosen, detailed engineering will begin following appropriate regulatory guidance. The plan will include characterisation information, namely: review of decommissioning alternatives; justification for the selected alternative; provision for regulatory compliance; predictions of personnel exposure, radioactive waste volume, and cost. Other activities are: scheduling, preparation for decommissioning operations; coordination, documentation, characterization report, feasibility studies, Decommissioning Plan, project daily report, radiological survey, airborne sampling records, termination survey of the site. The operations imply: identification and sequencing the operations on contaminated materials, storing on site the wastes, awaiting processing or disposal, and packaging of materials for transport to processing or disposal facilities.The key operations are: worker protection, health and safety program, review of planing work, work area assessment, work area controls

  12. Neutronic feasibility studies using U-Mo dispersion fuel (9 Wt % Mo, 5.0 gU/cm3) for LEU conversion of the MARIA (Poland), IR-8 (Russia), and WWR-SM (Uzbekistan) research reactors

    International Nuclear Information System (INIS)

    Bretscher, M.M.; Deen, J.R.; Hanan, N.A.; Matos, E.

    2000-01-01

    U-Mo alloys dispersed in an Al matrix offer the potential for high-density uranium fuels needed for the LEU conversion of many research reactors. On-going fuel qualification tests by the US RERTR Program show good irradiation properties of U-Mo alloy dispersion fuel containing 7-10 weight percent molybdenum. For the neutronic studies in this paper the alloy was assumed to contain 9 wt % Mo (U-9Mo) with a uranium density in the fuel meat of 5.00 gU/cm 3 which corresponds to 32.5 volume % U-9Mo. Fuels containing U-9Mo have been used in Russian reactors since the 1950's. For the three research reactors analyzed here, LEU fuel element thicknesses are the same as those for the Russian-fabricated HEU reference fuel elements. Relative to the reference fuels containing 80-90% enriched uranium, LEU U-9Mo Al-dispersion fuel with 5.00 gU/cm 3 doubles the cycle length of the MARIA reactor and increases the IR-8 cycle length by about 11%. For the WWR-SM reactor, the cycle length, and thus the number of fuel assemblies used per year, is nearly unchanged. To match the cycle length of the 36% enriched fuel currently used in the WWR-SM reactor will require a uranium density in the LEU U-9Mo Al-dispersion fuel of about 5.4 gU/cm 3 . The 5.00 gU/cm 3 LEU fuel causes thermal neutron fluxes in water holes near the edge of the core to decrease by (6-8)% for all three reactors. (author)

  13. Waste generated by the future decommissioning of the Magurele VVR-S Research Reactor

    International Nuclear Information System (INIS)

    Dragolici, F.; Turcanu, C.N.; Dragolici, A.C.

    2001-01-01

    Nuclear Research Reactor WWR-S from the National Institute of Research and Development for Physics and Nuclear Engineering 'Horia Hulubei', Bucharest-Magurele, was commissioned in July 1957 and it was shut down in December 1997. At the moment the reactor is in conservation state. During its operation this reactor worked at an average power of 2MW, almost 3216 h/year, producing a total thermal power of 230 x 10 3 MWh. No major modifications or improvements were made during the 40 years of operation to the essential parts of the reactor, respective to the primary cooling system, reactor vessel, active core and electronic devices. So, all components of the measure, control and protection systems are old, generally at the technical level of the 1950s, therefore a reason why in December 1997 the operation was ceased. At present, the reactor can be considered, by IAEA definition in the first stage (reactor shut down, but the vital functions are maintained and monitored). The survey is related to the second stage - restrictive use of the area. To develop a real decommissioning project, it was first necessary to evaluate the volume and the characteristics of the radioactive waste which will be generated. Radioactive waste generated during the decommissioning of Magurele WR-S research reactor may be classified as: Activated wastes (internal structures, horizontal channels and thermal column, biological shield); Contaminated wastes (primary circuit non-activated components, hot cells, some technological rooms as main hall, pumps room, radioactive material transfer areas, ventilation building and stack); Possibly contaminated materials from any area of reactor building and ventilation building. After 40 years of nuclear research activities, all such areas are suspected of contamination. The volume of wastes that will result from WWR-S Research Reactor decommissioning is summarized

  14. Generation of the problem-dependent data libraries for IFIN-HH WWR-S spent fuel storage criticality and dose calculation

    International Nuclear Information System (INIS)

    Ene, Daniela; Tigau, F.

    1998-01-01

    The methods used for the radioactivity inventory calculation and dose evaluation of the fuel elements irradiated in the WWR-S IFIN-HH reactor are discussed in this work. A particular attention is paid to the processed problem-dependent nuclear libraries. SAS2H, a complex sequence of the SCALE-4.3 code system containing the modules BONAMI - NITAWL - XSDRNPM - COUPLE - ORIGEN-S - XSDOSE, has been assimilated on the IFIN-HH computer and applied to update the ORIGEN-S libraries by producing problem-dependent processed data libraries needed to perform the depletion and shielding analysis. This sequence uses one of the eight associated data libraries of the SCALE-4.3 system according to the choice of the user. The method consists in the following analysis processes: i) lattice cell neutron analysis to produce the flux weighting spectrum for activation library updating; ii) update of the nuclear data constants of the ORIGEN-S libraries; iii) depletion and decay analysis for a specified fuel assembly and irradiation history in order to generate gamma and neutron source strength and spectra. iv) one-dimensional radial shielding calculation for the evaluation of the angular neutron and gamma flux at the surface of a spent fuel shipping cask and further calculation of the dose rates at various points outside the cask. An efficient alternative of the calculation sequence mentioned above is the ARP (Automatic Rapid Processing) method conceived in order to generate independently ORIGEN-S libraries and to reduce substantially the running time. The substance of this method is the generation of the problem-dependent libraries from basis libraries a priori created by SAS2H for specific fuel assembly type and further interpolation of two independent variables, enrichment and burnup. Specific applications concerning WWR-S spent fuel were performed: i) generation of three problem-dependent libraries for the S-36 fuel assembly taking into account the maximum value of the burnup of this

  15. Calculational investigations and analysis of characteristics of research reactor WWR-M as a source of neutrons for solution of scientific and applied tasks

    International Nuclear Information System (INIS)

    Vorona, P.M.; Razbudej, V.F.

    2010-01-01

    Calculational studies and analysis of the neutron fields of WWR-M research reactor of the Institute for Nuclear Research, National Academy of Sciences of Ukraine, as a basic nuclear facility for performing the fundamental and applied investigations and for experimentalindustrial production of radioisotope products for various spheres of application are carried out. The calculations are carried out by the method of statistic tests (Monte Carlo) applying the computer program MCNP-4C. The data on the spectra and the neutron flux density values at the 10 MW reactor power for all technological facilities designed for the works with neutrons: 19 vertical experimental channels for irradiation of specimens and 10 horizontal channels for beams extraction from the reactor are obtained. The effect of the neutron traps (water cavities) mounted in the core on the characteristics of the extracted from the reactor beams is demonstrated. Recommendations associated with optimization of the reactor core are adduced for amplification of its capabilities as a neutron source in experimental researches.

  16. Encapsulation technology of MR6 spent fuel and quality analysis of the EK-10 and WWR-SM spent fuel stored more than 30 years in wet conditions

    Energy Technology Data Exchange (ETDEWEB)

    Borek-Kruszewska, E.; Bykowski, W.; Chwaszczewski, S.; Czajkowski, W.; Madry, M. [Institute of Atomic Energy, Otwock -Swierk (Poland)

    2002-07-01

    The research reactor MARIA has been in operation for more than twenty years and all the spent fuel assemblies used since the first commissioning of the reactor are stored in wet facility on site. The present paper deals with the spent fuel MR-6 encapsulation technology in MARIA reactor. The encapsulated spent MR-6 fuel will be stored under water in the same pool unless some other solution is available. The capsules made of stainless steel are capable to accommodate one MR-6 fuel assembly. The encapsulation process is performed in the hot cell by the MARIA reactor. The spent fuel having its leg cut off is loaded to the transport cylinder manually and next transferred to a trolley. The trolley is moving to a position directly below the entrance to the hot cell and the spent fuel is entering the hot cell. The spent fuel assembly is then put into the drying cell. Dried out spent fuel is moved into the capsule mounted on the grip of the machine. Next, the capsule lid is pressed in and welded. After the leak test and filling up with helium the capsule returns from the hot cell to the pool. The hermetic capsule is sunk back into the water and positioned in the separator . The results presented earlier show, that the limiting time of WWR-SM and Ek-10 type spent fuel residence in wet storage is about 40-45 years. Therefore, the systematic quality investigation of all Ek-10 fuel elements and WWR-SM fuel assemblies discharged from EWA reactor in the period of 1959-1969 was performed. Altogether, about 2500 Ek-10 fuel elements and 47 WWR-SM fuel assemblies were investigated. The results of these investigations are presented in the present work. The sipping test, visual investigation and ultrasonic techniques were used for that purpose. The radioactive isotope Cs-137 was used as the indicator of fission product release from the fuel assembly. Taking into account the value of Cs-137 release from damaged WWR-SM fuel assembly the criteria of damaged fuel assembly were proposed. It

  17. Radiologic states of the WWR-S Bucharest Reactor following definitive shutdown

    International Nuclear Information System (INIS)

    Garlea, C.; Kelerman, C.; Mocioiu, D.; Garlea, I.

    2001-01-01

    The definitive shutdown of a reactor raises problems related to the management of the radioactive inventory. To define the radioactive inventory contained in the burned nuclear fuel and in the neutron activated structural materials computation methods are to be used. Besides the radioactive inventory contained in the main block of the reactor, the one due to the primary circuit contaminated mainly with fission products and corrosion products activated in the reactor core, transported and deposed on the components of the cooling primary circuit should be added. Also another component of the radioactive inventory intervenes, namely, the one due to the contamination of the technological rooms used for various operations the nuclear activities (hot cells, pump room, reactor hall, passage ways to the hot cells and for radioactive source, radioisotope and radioactive waste transport). The activities which made used of the neutron and gamma fluxes for radioisotope production, materials irradiation, research, component testing, resulted in radioactive waste, technological or accidental contaminations of the technological rooms of the reactor. Inspections and current repair interventions resulted also in radioactive waste an contaminations. Consequently systematic measurements with qualified equipment dedicated to alpha, beta, gamma contamination measurements as well as to dose rates determinations for the personnel exposed are necessary. Irrespective of the duration of the reactor conservation or shutdown, the radiologic monitoring should continue. This work presents the results obtained by the research group 'Restoration of Nuclear Sites', working with the IFIN-HH, regarding both the radioactive inventory calculation and measurements of contamination of technological rooms and environment in the reactor vicinity

  18. Calculation of prefabricated part of WWR-K reactor building

    International Nuclear Information System (INIS)

    Belyashova, N.N.; Aptikaev, F.F.; Kopnichev, Yu.F.

    1998-01-01

    According of factual characteristics a strength and deformation of over-land part of carrier constructions under construction movement is defined. Direct dynamical calculation of design elements under action of inertial loads from supports shifts shows, that seismic stability of enclosing construction is not ensured. Possibly practically total collapse of coating construction is possibly, under which following levels of damages of internal design constructions of reactor central room have been forecasted: 1. Fall of destroyed design construction on reactor vessel in time moment (1.56-1.59 s) after coming to building of earthquake seismic waves of 10 balls. 2. It is possibly cracks formation in radial direction in lower part of reactor cap, but destroying of cap does not incident; 3. It is possibly cracks formation within stretched concrete zone of reactor construction at the mark from - 0.859 up to 0.100. Destroy of concrete's compressive zone of reactor construction have not being expected. 4. Collapse of reactor first contour coating constructions have not being expected

  19. Investigation of neutron fluence using fluence monitors for irradiation test at WWR-K

    International Nuclear Information System (INIS)

    Romanova, N.K.; Takemoto, N.

    2013-01-01

    Irradiation test of a Si ingot is planned using WWR-K in Institute of Nuclear Physics Republic of Kazakhstan (INP RK) to develop an irradiation technology for Si semiconductor production by Neutron Transmutation Doping (NTD) method in the framework of an international cooperation between INP RK and Japan Atomic Energy Agency (JAEA), Japan. It is possible to irradiate the Si ingot of 6 inch in diameter at the K-23 irradiation channel in the WWR-K. The preliminary irradiation test using 4 Al ingots was performed to evaluate the actual neutronic irradiation field at the K-23 channel in the WWR-K. Each Al ingot has the same dimension as the Si ingot, and 15 fluence monitors are equipped in it. Iron wire and aluminum-cobalt wire are inserted into them, and it is possible to evaluate both fast and thermal neutron fluxes by measurement of these radiation activities after irradiation. This report described the results of the preliminary irradiation test and the neutronic calculations by Monte Carlo method in order to evaluate the neutronic irradiation field in the irradiation position for the silicon ingot at the channel in the WWR-K. (authors)

  20. Determination of the gamma-ray flux of the stopped WWR-SM reactor by color center production in LiF

    International Nuclear Information System (INIS)

    Mussaeva, M.A.; Kalannov, M.U.; Ibragimova, E.M.; Karabaev, Kh.Kh.

    2004-01-01

    Full text: Gamma-radiation with a wide energy spectrum, accompanying neutron flux in the nuclear reactor, is known to result in radiation heating of materials. It is usually detected either by calorimetry or by an ionizing chamber maintained in the active zone while the reactor works and high-energy neutrons also contribute into ionization. The aim of this research was to separate the gamma-component from the neutron flux upon stopping the WWR-SM reactor and to determine the gamma-intensity both with the ionization chamber and the well-known dosimeter LiF crystal, and also by comparing with the effect of monochromatic 60 Co gamma-radiation of the known flux and dose. For LiF with small Z the photoelectric effect is weak, and Compton scattering prevails. Both the optical absorption and photo-luminescence techniques together with micro-hardness and X-ray diffraction analysis were used for measuring the structure defect generation rate in the irradiated crystals, which is proportional to the gamma-intensity. Fluorine vacancy trapping electron is the well-known stable F-center responsible for the isolated absorption band at 250 nm and induced by radiolysis mechanism. The sequential irradiations and measurements were done within 150 hours after the moment of the reactor quenching. The dose dependence of the absorption band was found to be linear up to the dose of 10 6 R. The F-center concentration as a measure of an accumulated dose was calculated by the Smakula formula. At higher doses another band at 440 nm appears like that for 60 Co irradiation, which is responsible for unstable F 2 and F 3 centers formed due to coagulation of F-centers. X-diffraction analysis revealed twin structure in (111) plane. Yet the micro-hardness of the gamma-irradiated samples did not change noticeably. For higher doses the photo-luminescence band at 650 nm was also used as a dosimetric item. The luminescence kinetics has a fast nanosecond scale component and a weak tail in a microsecond

  1. [Radiation ecological environment in the Republic of Kazakhstan in the vicinity of the reactors and on the territory of the Semipalatinsk Test Site].

    Science.gov (United States)

    Kim, D S

    2012-01-01

    The results of research into the environmental conditions in the regions of location of the pressurized water reactor WWR-K, fast neutron breeder BN-350 and on the territory of the Semipalatinsk Test Site are represented. The effects of the exposure to aerosol emissions from WWR-K and BN-350 reactors on the environment are summarized. We present some arguments in favor of the safe operation of fission reactors in compliance with the rules and norms of nuclear and radiation protection and the efficient disposal of radioactive waste on the territory of the Republic.

  2. Feasibility study for LEU conversion of the WWR-K reactor at the Institute of Nuclear Physics in Kazakhstan using a 5-tube fuel assembly

    International Nuclear Information System (INIS)

    Hanan, N.A.; Liaw, J.R.; Matos, J.E.

    2005-01-01

    A feasibility study by the RERTR program for possible LEU conversion of the 6 MW WWR-K reactor concludes that conversion is feasible using an LEU 5-tube Russian fuel assembly design. This 5-tube design is one of several LEU fuel assembly designs being studied (Ref. 1) for possible use in this reactor. The 5-tube assembly contains 200 g 235 U with an enrichment of 19.7% in four cylindrical inner tubes and an outer hexagonal tube with the same external dimensions as the current HEU (36%) 5-tube fuel assembly, which contains 112.5 g 235 U. The fuel meat material, LEU UO 2 -Al dispersion fuel with ∼ 2.5 g U/cm 3 , has been extensively irradiation tested in a number of reactors with uranium enrichments of 36% and 19.7%. Since the 235 U loading of the LEU assemblies is much larger than the HEU assemblies, a smaller LEU core with five rows of fuel assemblies is possible (instead of six rows of fuel assemblies in the HEU core). This smaller LEU core would consume about 60% as many fuel assemblies per year as the current HEU core and provide thermal neutron fluxes in the inner irradiation channels that are ∼ 17% larger than with the present HEU core. The current 21 day cycle length would be maintained and the average discharge burnup would be ∼ 42%. Neutron fluxes in the five outer irradiation channels would be smaller in the LEU core unless these channels can be moved closer to the LEU fuel assemblies. Results show that the smaller LEU core would meet the reactor's shutdown margin requirements and would have an adequate thermal-hydraulic safety margin to onset of nucleate boiling. (author)

  3. The CAIRO4 study

    DEFF Research Database (Denmark)

    't Lam-Boer, Jorine; Mol, Linda; Verhoef, Cornelis

    2015-01-01

    stages of the disease. We here propose a randomized trial in order to demonstrate that resection of the primary tumour improves overall survival. METHODS/DESIGN: The CAIRO4 study is a multicentre, randomized, phase III study of the Dutch Colorectal Cancer Group (DCCG). Patients with synchronous...... objective of this study is to determine the clinical benefit in terms of overall survival of initial resection of the primary tumour. Secondary endpoints include progression free survival, surgical morbidity, quality of life and the number of patients requiring resection of the primary tumour in the control...... arm. DISCUSSION: The CAIRO4 study is a multicentre, randomized, phase III study that will assess the benefit of resection of the primary tumour in patients with synchronous metastatic CRC. TRIAL REGISTRATION: The CAIRO4 study is registered at clinicaltrials.gov (NCT01606098)....

  4. Topographical Photography in Cairo: The Lens of Beniamino Facchinelli

    OpenAIRE

    Seif, Ola

    2017-01-01

    Nineteenth century photographs of Cairo, especially the last quarter of it, were commonly represented in compiled albums which followed to a fair extent, visually, the section on Egypt in Francis Frith’s publications. Typically, they contained an assortment of topics revolving around archaeological monuments from Upper Egypt, the pyramids and panoramic views of Cairo such as the Citadel, in addition to façades and courtyards of Islamic monuments, mainly the mosques of Sultan Hasan and Ibn Tul...

  5. Computerized reactor power regulation with logarithmic controller

    International Nuclear Information System (INIS)

    Gossanyi, A.; Vegh, E.

    1982-11-01

    A computerized reactor control system has been operating at a 5 MW WWR-SM research reactor in the Central Research Institute for Physics, Budapest, for some years. This paper describes the power controller used in the SPC operating mode of the system, which operates in a 5-decade wide power range with +-0.5% accuracy. The structure of the controller easily limits the minimal reactor period and produces a reactor transient with constant period if the power demand changes. (author)

  6. Assembling a Revolution: Graffiti, Cairo and the Arab Spring

    Directory of Open Access Journals (Sweden)

    John Lennon

    2014-03-01

    Full Text Available This essay examines the ways revolutionary desire was articulated and interpreted through graffiti in Cairo, Egypt during the Arab Spring and its immediate aftermath. For writers in Cairo, graffiti was one of many in a constellation of resistances that undermined everyday life in Hosni Mubarak’s Egypt and the SCAF-controlled interim government. Ordinary surfaces of the city were illegally marked, displaying revolutionary potentiality by allowing the seemingly powerless rhetorical openings of engagement. Far from being a monolithic discourse, graffiti created geographies of material protest that were locally enacted but globally contextualized. Political graffiti, like the overall protests of the Arab Spring, emerged in large numbers at particular moments, but its numerous roots spread distinctly into the past. First contextualizing Cairo graffiti as a tool for revolutionary protest, the article then examines specific writers (Mahmoud Graffiti, Ganzeer, particular ‘battleground' spaces (Tahrir Square, Mohamed Mahmoud Street, different graffiti mutations (tags, pieces, murals and contrary aesthetic manipulations of the form (‘No Walls’ campaign, graffiti advertisements by multinational corporations in order to assemble a graffiti scene in Cairo as it follows the ebbs and flows of revolutionary desire.

  7. The Rossendorf research reactor. Operating and dismantling from a point of view of the emission control; Der Rossendorfer Forschungsreaktor. Betrieb und Rueckbau aus Sicht der Emissionsueberwachung

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, B.; Beutmann, A.; Kaden, M.; Scheibke, J. [VKTA, Dresden (Germany); Boessert, W.; Jansen, K.; Walter, M.

    2016-07-01

    The Rossendorf research reactor went in operation in 1957 as GDR's first nuclear reactor and Germanys second after FRM Garching. It was a heterogeneously structured, light-water moderated and cooled tank-reactor of the Soviet type WWR-S. During his time of operation, he served both the research and the production of radioisotopes. The history of exhaust air emission monitoring and its results are presented. With view to the decommissioning time selected results are discussed. The estimated discharges are compared by the actually recognized.

  8. The application of calorimetrical methods in nuclear technology and dosimetry

    International Nuclear Information System (INIS)

    Kott, J.; Krett, V.; Novotny, J.; Kovar, Z.; Jirousek, V.

    1985-01-01

    The report reviews theoretical as well as experimental research activities devoted to the possibilities of measuring reactor neutron and photon fields using thermic detectors based on calorimetric principle. There have been worked out theoretical principles of a reactor measuring probe intended in the first place to measuring neutron fluxes under operational temperatures inside power and research reactors, and a new philosophy of measurement has been elaborated. In addition, the report presents the experimental results as obtained on research reactors WWR-S, WWR-SM, RA, and Czechoslovak power reactor A-1 and GDR power reactor WWR-2. These results are given in connection with a newly proposed technique of reactor neutron field detection. The second part of the report presents results of works concerning beam dosimetry with the use of calorimeters

  9. Probabilistic earthquake hazard analysis for Cairo, Egypt

    Science.gov (United States)

    Badawy, Ahmed; Korrat, Ibrahim; El-Hadidy, Mahmoud; Gaber, Hanan

    2016-04-01

    Cairo is the capital of Egypt and the largest city in the Arab world and Africa, and the sixteenth largest metropolitan area in the world. It was founded in the tenth century (969 ad) and is 1046 years old. It has long been a center of the region's political and cultural life. Therefore, the earthquake risk assessment for Cairo has a great importance. The present work aims to analysis the earthquake hazard of Cairo as a key input's element for the risk assessment. The regional seismotectonics setting shows that Cairo could be affected by both far- and near-field seismic sources. The seismic hazard of Cairo has been estimated using the probabilistic seismic hazard approach. The logic tree frame work was used during the calculations. Epistemic uncertainties were considered into account by using alternative seismotectonics models and alternative ground motion prediction equations. Seismic hazard values have been estimated within a grid of 0.1° × 0.1 ° spacing for all of Cairo's districts at different spectral periods and four return periods (224, 615, 1230, and 4745 years). Moreover, the uniform hazard spectra have been calculated at the same return periods. The pattern of the contour maps show that the highest values of the peak ground acceleration is concentrated in the eastern zone's districts (e.g., El Nozha) and the lowest values at the northern and western zone's districts (e.g., El Sharabiya and El Khalifa).

  10. The American University in Cairo: 1919-1987.

    Science.gov (United States)

    Murphy, Lawrence R.

    The history of The American University in Cairo, an accredited, private liberal arts institution and the largest U.S. university outside the United States, is presented. The majority of both students and faculty are Egyptian, but the university community is international with members from the Middle East, Europe, Asia, Africa, and America. The…

  11. en cementos el Cairo S.A.

    Directory of Open Access Journals (Sweden)

    ALEXANDER CORREA

    2007-01-01

    Full Text Available Este artículo tiene como finalidad difundir los estudios de repetibilidad y reproducibilidad de la medida, conocidos como Estudios R&R, a partir del diseño experimental. Con su aplicación se busca identificar y disminuir la variabilidad presente en las mediciones de los ensayos que se realizan en los laboratorios de control de calidad. La efectividad de este tipo de estudios radica principalmente en el control que se haga de las variables que intervienen en los procesos de medición, estas variables son el medio ambiente en que son desarrolladas, el estado de los equipos e implementos utilizados, la capacitación que tiene el operario, el uso de material homogéneo y la aplicación de un método normalizado. El artículo describe una secuencia ordenada de los pasos que se deben seguir antes y durante la realización de un Estudio R&R, además muestra la aplicación de esta metodología en la empresa Cementos El Cairo, donde fueron realizadas dos corridas del método a la prueba finura de cemento, en la primera se identifica la variabilidad presente en los ensayos, de este primer acercamiento surgen algunos ajustes que son implementados rápidamente por la empresa y con el afán de mejorar estos procesos es planeada la segunda corrida, terminado este segundo ciclo se obtiene, aunque en poca proporción, una variabilidad menor a la del primer ciclo.

  12. Irradiation facilities for the production of radioisotopes for medical purposes and for industry at the Rossendorf Research Reactor

    International Nuclear Information System (INIS)

    Hieronymus, W.

    2007-01-01

    In 1955, the Government of the German Democratic Republic initiated radioisotope production. With that decision, the following plants received their go ahead: - Research reactor with its user facilities; - Cyclotron with its specific facilities; - Institute for radiochemistry; - Library, lecture hall, workshops and administration buildings supporting the necessary scientific and administrative environment. The Zentralinstitut fuer Kerntechnik (ZfK), also known as the Central Institute for Nuclear Technology, was founded at Rossendorf near Dresden, Germany, to house all those plants. The Rossendorf Research Reactor (RFR) was constructed in 1956-1957. That endeavour was enabled by the technological support of the former USSR under a bilateral agreement which included the delivery of a 2 MW research reactor of the WWR-S design

  13. Cost effective safety enhancements for research reactors in Uzbekistan and Kazakhstan - results of a joint program with US DOE

    International Nuclear Information System (INIS)

    Earle, O.K.; Carlson, R.B.; Rakhmanov, A.; Salikhbaev, U.S.; Chernyaev, V.; Chakrov, P.

    2004-01-01

    Full text: The US Department of Energy's Office of International Nuclear Safety and Cooperation established the Integrated Research Reactor Safety Enhancement Program (IRRSEP) in February 2002 to support U.S. nonproliferation goals by (1) implementing safety upgrades, or (2) assisting with the safe shutdown and decommissioning of foreign test and research reactors which present security concerns. IRRSEP's key program components are: Phase I: Self-evaluation by facility using provided checklists followed by prioritization to identify the 20 highest risk facilities; Phase II: Site visits with technical evaluation to finalize a list of projects that will enhance safety consistent with IAEA observations; Phase III: Corrective measures to implement the projects. Phases I, II and III are accomplished on a rolling basis, such that work is ongoing at three or four reactors per year. IRRSEP's key objective is to resolve the highest-priority nuclear safety issues at the most vulnerable foreign research reactors as quickly as possible. The prioritization methodology employed identified which research reactors fell into this category. The corrective measures mutually developed with the host facility are based on the premise of developing a sustainable infrastructure within each country to deal with its own nuclear material safety, security, and response issues in the future. IRRSEP also assists in creating an international framework of cooperation and openness between research and test reactor operators, and national and international regulators. The initial projects under IRRSEP are underway at research reactors in Kazakhstan, Uzbekistan, and Romania. This paper focuses on the projects undertaken at the WWR-K research reactor at the Institute of Nuclear Physics in Alatau, Kazakhstan and the WWR-SM research reactor at the Institute of Nuclear Physics in Ulugbek, Uzbekistan. These projects demonstrate the success and cost effectiveness of the IRRSEP program

  14. Cost effective safety enhancements for research reactors in Uzbekistan and Kazakhstan - results of a joint program with US DOE

    International Nuclear Information System (INIS)

    Earle, O.K.; Carlson, R.B.; Rakhmanov, A.; Salikhbaev, U.S.; Chernyaev, V.; Chakrov, P.

    2004-01-01

    The US Department of Energy's Office of International Nuclear Safety and Cooperation established the Integrated Research Reactor Safety Enhancement Program (IRRSEP) in February 2002 to support U.S. nonproliferation goals by implementing safety upgrades, or assisting with the safe shutdown and decommissioning of foreign test and research reactors which present security concerns. IRRSEP's key program components are: Phase I: Self-evaluation by facility using provided checklists followed by prioritization to identify the 20 highest risk facilities; Phase II: Site visits with technical evaluation to finalize a list of projects that will enhance safety consistent with IAEA observations; Phase III: Corrective measures to implement the projects. Phases I, II and III are accomplished on a rolling basis, such that work is ongoing at three or four reactors per year. IRRSEP's key objective is to resolve the highest-priority nuclear safety issues at the most vulnerable foreign research reactors as quickly as possible. The prioritization methodology employed identified which research reactors fell into this category. The corrective measures mutually developed with the host facility are based on the premise of developing a sustainable infrastructure within each country to deal with its own nuclear material safety, security, and response issues in the future. IRRSEP also assists in creating an international framework of cooperation and openness between research and test reactor operators, and national and international regulators. The initial projects under IRRSEP are underway at research reactors in Kazakhstan, Uzbekistan, and Romania. This paper focuses on the projects undertaken at the WWR-K research reactor at the Institute of Nuclear Physics in Alatau, Kazakhstan and the WWR-SM research reactor at the Institute of Nuclear Physics in Ulugbek, Uzbekistan. These projects demonstrate the success and cost effectiveness of the IRRSEP program

  15. Creation of reactor's reliable system of emergency energy supply

    International Nuclear Information System (INIS)

    Batyrbekov, G.A.; Brovkin, A.Yu.; Petukhov, V.K.; Chekushin, A.I.; Chernyaev, V.P.; Yagotinets, N.A.

    1998-01-01

    System of reliable power supply of the WWR-K reactor complex is described, which completely provides safety operation of reactor equipment in the case of total voltage loss from external power transmission lines as well as under destruction of accumulation batteries by earthquake more than 6 balls. Switching on in operation of diesel-generators and system of constant current supply from accumulator batteries is occurred automatically under cessation of voltage supply from centralized power system. Reliable reactor dampening in case it work on capacity has been ensured. Reactor cooling under its emergency shutdown during both the partial or the total loss of coolant in first counter has been carried out. Under full coolant loss the system of emergency reactor cooling has been switched on in operation

  16. Update earthquake risk assessment in Cairo, Egypt

    Science.gov (United States)

    Badawy, Ahmed; Korrat, Ibrahim; El-Hadidy, Mahmoud; Gaber, Hanan

    2017-07-01

    The Cairo earthquake (12 October 1992; m b = 5.8) is still and after 25 years one of the most painful events and is dug into the Egyptians memory. This is not due to the strength of the earthquake but due to the accompanied losses and damages (561 dead; 10,000 injured and 3000 families lost their homes). Nowadays, the most frequent and important question that should rise is "what if this earthquake is repeated today." In this study, we simulate the same size earthquake (12 October 1992) ground motion shaking and the consequent social-economic impacts in terms of losses and damages. Seismic hazard, earthquake catalogs, soil types, demographics, and building inventories were integrated into HAZUS-MH to produce a sound earthquake risk assessment for Cairo including economic and social losses. Generally, the earthquake risk assessment clearly indicates that "the losses and damages may be increased twice or three times" in Cairo compared to the 1992 earthquake. The earthquake risk profile reveals that five districts (Al-Sahel, El Basateen, Dar El-Salam, Gharb, and Madinat Nasr sharq) lie in high seismic risks, and three districts (Manshiyat Naser, El-Waily, and Wassat (center)) are in low seismic risk level. Moreover, the building damage estimations reflect that Gharb is the highest vulnerable district. The analysis shows that the Cairo urban area faces high risk. Deteriorating buildings and infrastructure make the city particularly vulnerable to earthquake risks. For instance, more than 90 % of the estimated buildings damages are concentrated within the most densely populated (El Basateen, Dar El-Salam, Gharb, and Madinat Nasr Gharb) districts. Moreover, about 75 % of casualties are in the same districts. Actually, an earthquake risk assessment for Cairo represents a crucial application of the HAZUS earthquake loss estimation model for risk management. Finally, for mitigation, risk reduction, and to improve the seismic performance of structures and assure life safety

  17. Russian RERTR program as a part of Joint US DOE-RF MINATOM collaboration on elimination of the threat connected to the use of HEU in research reactors

    International Nuclear Information System (INIS)

    Arkhangelsky, N.

    2002-01-01

    The Russian RERTR Program started at the end of 70's, the final goal of the program is to eliminate supplies of HEU in fuel elements and assemblies for foreign research reactors that were designed according to Russian projects. Basic directions of the work include: completion of the development of the fuel elements and assemblies on a basis of uranium dioxide; development of the fuel on a basis of U-Mo alloy; and development of pin type fuel elements. Fuel assemblies of WWR-M2 type with LEU were developed and qualified for using in foreign research reactors that use such type of fuel assemblies. These assemblies are ready for the supplying several operating foreign research reactors. There are more than 20 sites in Eastern European countries, former Soviet republics and another countries that have big amount of Russian origin HEU in fresh and spent fuel. The problem of the shipment of SNF from sites of research reactors is also very important for domestic Russian research reactors. More than ten years from its beginning the Russian RERTR program developed practically independently from the international RERTR program and only at the begin of 90's the Russian specialists started to contact with foreign scientists and the exchange of the scientific information has become more intensive. In September 1994, representatives of Minatom and DOE signed a protocol of intent to reduce an enrichment of uranium in research reactors. The main aspects of collaboration involve: Several domestic Russian research reactors such as WWR-M, IR-8 and others were investigated from the point of view of possibility of reducing of enrichment; financial support of the program from US DOE which is insufficient. The important part of international collaboration is the import of Russian origin spent and fresh fuel of research reactors to Russia. In August 2002 an impressive result of the Russian-American collaboration with support of IAEA and with the help and assistance of Yugoslavian side was

  18. Neutron flux calculations for the Rossendorf research reactor in (hex)- and (hex,z)-geometry using SNAP-3D

    International Nuclear Information System (INIS)

    Koch, R.; Findeisen, A.

    1986-04-01

    The multigroup neutron diffusion theory code SNAP-3D has been used to perform time independent neutron flux and power calculations of the 10 MW Rossendorf research reactor of the type WWR-SM. The report describes these calculations, as well as the actual reactor configuration, some details of the code SNAP-3D, and two- and three-dimensional reactor models. For evaluating the calculations some flux values and control rod worths have been compared with those of measurements. (author)

  19. Transient behaviour study program of research reactors fuel elements at the Hydra Pulse Reactor

    International Nuclear Information System (INIS)

    Khvostionov, V.E.; Egorenkov, P.M.; Malankin, P.V.

    2004-01-01

    Program on behavior study of research reactor Fuel Elements (FE) under transient regimes initiated by excessive reactivity insertion is being presented. Program would be realized at HYDRA pulse reactor at Russian Research Center 'Kurchatov Institute' (RRC 'K1'). HYDRA uses aqueous solution of uranyl sulfate (UO 2 SO 4 ) as a fuel. Up to 30 MJ of energy can be released inside the core during the single pulse, effective power pulse width varying from 2 to 10 ms. Reactor facility allows to investigate behaviour of FE consisting of different types of fuel composition, being developed according to Russian RERTR. First part of program is aimed at transient behaviour studying of FE MR, IRT-3M, WWR-M5 types containing meats based on dioxide uranium in aluminum matrix. Mentioned FEs use 90% and 36% enriched uranium. (author)

  20. Status of Dalat research reactor and progress of new reactor plan in Vietnam

    International Nuclear Information System (INIS)

    Dien, Nguyen Nhi; Vien, Luong Ba

    2005-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500-kW pool-type reactor loaded with the Soviet WWR-M2 Fuel Assemblies (FA), moderated and cooled by light water. The reactor was reconstructed from the USA 250-kW TRIGA Mark-II reactor built in early 1960s. The first criticality of the renovated reactor was achieved on 1 st November 1983, and then on 20 March 1984 the reactor was officially inaugurated and its activities restarted. During the last twenty years, the DNRR has played an important role as a large national research facility to implement researches and applications, and its utilization has been broadened in various fields of human life. However, due to the limitation of the neutron flux and power level, the out-of date design of the experimental facilities and the ageing of the reactor facilities, it cannot meet the increasing user's demands even in the existing utilization areas. In addition, the utilization demands of the Research Reactor (RR) will be increased along with the development of the nation's economy growth. In this aspect, it is necessary to have in Vietnam a new high performance multipurpose RR with a sufficient neutron flux and power level. According to the last draft of a national strategy for atomic energy development submitted to the Government for consideration and approval, it is expected that a new high power RR would be put into operation before 2020. The operation and utilization status of the DNRR is presented and some preliminary results of the national research project on new reactor plan for Vietnam are discussed in this paper

  1. Experience in reactor research and development programs as educational system for thermohydraulic engineering

    International Nuclear Information System (INIS)

    Zaki, G.M.; Fikry, M.M.

    1977-01-01

    A reactor development program within a research reactor facility can be used for personnel training on the operation of power reactors and research in the different fields of nuclear science and engineering. A training program is proposed where reactor maintenance and operation, in addition to conducting development programs and executing projects, are utilized for forming specialized groups. The paper gives a short survey of a heat transfer program where out of pile and in-core studies are conducted along with two-phase flow investigations. This program covers the main requirements for WWR (water cooled and moderated reactor) power uprating and furnishes basic knowledge on power reactor thermal parameters. The major facilities for conducting similar programs devoted to education are mentioned

  2. Cairo conference.

    Science.gov (United States)

    McMichael, A J

    1994-09-03

    The United Nations Conference on Population and Development in Cairo in September, 1994, will evoke criticism of the inability of governments to act quickly enough to avert demographic and environmental crises. Rapid population growth has clear implications for public health. Globally there now occur anthropogenic changes in atmospheric composition, the degradation of fertile lands and ocean fisheries, an accelerating loss of biodiversity, and the social and ecological problems of massive urbanization. In the future, per capita consumption levels will increase in burgeoning populations of developing countries, thus adding to the environmental impacts of overconsuming rich countries. By the end of the decade there will be over six billion people, of whom one half will live in cities. These demographic and environmental trends, if translated into climatic change, regional food shortages, and weakened ecosystems, would adversely affect human health. The World Health Organization is likely to concentrate only on accessible family planning and promotion of health for women and families. Continuing asymmetric child-saving aid, unaccompanied by substantial aid to help mobilize the social and economic resources needed to reduce fertility, may delay the demographic transition in poor countries and potentiate future public health disasters. As a result of recent reductions in fertility, even in Sub-Saharan Africa, average family sizes have been halved. Yet the demographic momentum will double population by 2050. The biosphere is a complex of ecosystems and, if unsustained, it could not fulfill the productive, cleansing, and protective functions on which life depends. The Cairo conference must therefore recognize that sustaining human health is a prime reason for concern about population growth and models of economic development.

  3. Copenhagen−Cairo on a roundtrip

    DEFF Research Database (Denmark)

    Greenwood, Maja Touzari Janesdatter; Wæver, Ole

    2013-01-01

    and Strategic Studies in Cairo in 2010, securitization theory was challenged on two levels: both through its employment to analyse and act politically in a Middle Eastern context, and through the attempt to do so during and after the Arab Spring, when the entire Egyptian security sector was being re...

  4. Estimation of the outlooks for large-scale transmutation of fission-produced iodine

    CERN Document Server

    Galkin, B Y; Kolyadin, A B; Kocherov, N P; Lyubtsev, R I; Hosov, A A; Rimskij-Korsakov, A A

    2002-01-01

    To obtain data necessary for estimating sup 1 sup 2 sup 9 I transmutation efficiency in nuclear reactors the effective neutron capture cross section on sup 1 sup 2 sup 9 I isotope in neutral spectrum of the WWR-M reactor was determined. The calculated value of sup 1 sup 2 sup 9 I capture cross section, averaged by neutron spectrum in beryllium reflector of the WWR-M reactor, made up 17.8+-3.2 barn. On the basis of experimental data and estimations it was shown that in neutron flux 10 sup 1 sup 4 1/(cm sup 2 s) transmutation of iodine -129 loaded in the course of one year can amount to approximately 25%

  5. The text of the Cairo declaration. Adopted on the occasion of the signing of the African Nuclear-Weapon-Free Zone Treaty (the Treaty of Pelindaba) Cairo, 11 April 1996

    International Nuclear Information System (INIS)

    1996-01-01

    As requested by the Resident Representative of Egypt to the International Atomic Energy Agency, the document reproduces the text of the 'Cairo Declaration' which was adopted by the African States signatories of the African Nuclear-Weapon-Free Zone Treaty (the Treaty of Pelindaba) on the occasion of the signature of the Treaty on 11 April 1996 in Cairo

  6. The feasibility of using a Fourier RTOF spectrometer at a low-power research reactor

    International Nuclear Information System (INIS)

    Maayouf, R.M.A.; Priesmeyer, H.G.; Kudryashev, V.A.

    1991-01-01

    The present situation of Fourier time-of-flight (TOF) spectrometry is discussed using the FSS spectrometer as example. The use of the Fourier reverse TOF spectrometry, as an efficient tool for studying condensed matter, at a 2 MW (WWR-S type) reactor is also assessed. The arrangement of the RTOF spectrometer, which could be successfully used at such type of reactor, is introduced. The suggested arrangement applies a neutron guide tube of 24 m length and allows for effective luminosity 2.4.10 6 at a flight path distance of 3.6 m. The number of neutrons scattered from a sample (5 cm 3 in volume) and incident on the detector system, as estimated for the suggested arrangement, is ∝1.6.10 3 n/sec. Such high counting rate allows to measure a diffraction spectrum within less than an hour. (orig.) With 12 figs [de

  7. Darfur Refugees in Cairo: Mental Health and Interpersonal Conflict in the Aftermath of Genocide

    Science.gov (United States)

    Meffert, Susan M.; Marmar, Charles R.

    2009-01-01

    Hundreds of thousands of Darfur people affected by the Sudanese genocide have fled to Cairo, Egypt, in search of assistance. Collaborating with Africa and Middle East Refugee Assistance (AMERA), the authors conducted a mental health care needs assessment among Darfur refugees in Cairo. Information was collected using individual and focus group…

  8. Neutron spectra measurements and neutron flux monitoring for radiation damage purposes

    International Nuclear Information System (INIS)

    Osmera, B.; Petr, J.; Racek, J.; Rumler, C.; Turzik, Z.; Franc, L.; Holman, M.; Hogel, J.; Kovarik, K.; Marik, P.; Vespalec, R.; Albert, D.; Hansen, V.; Vogel, W.

    1979-09-01

    Neutron spectra were measured for the TR-0, WWR-S and SR-0 experimental reactors using the recoil proton method, 6 Li spectrometry, scintillation spectrometry and activation detectors in a variety of conditions. Neutron fluence was also measured and calculated. (M.S.)

  9. Aspects of intellectual property related to the TRIGA reactor in Romania

    International Nuclear Information System (INIS)

    Chirita, Ion

    2008-01-01

    Full text: A TRIGA - type research reactor has been operating in Pitesti since 1979. In Romania, the first research reactor - of the WWR-C type - has been operating since 1957. Both these reactors have contributed to the formation of well - trained specialists, whose works constitute an important intellectual and industrial property. Institute for Nuclear Research (formerly INT, then INPR) is the holder of several published patents, such as: Procedure for decontamination of water and primary circuits of irradiation devices; Reconditioning of ion exchangers; Nozzle for flow water gaugers; Oscillating electromagnetic pump; Facility for determining nuclear fuel burnup; Portable monitor for contamination measurements; Cable joints with biological protection; Anti-seismic and thermal connection; Automatic facility for nuclear fuel irradiation testing; Method for determining power distribution specific for research rector fuel elements; Tight end-fittings; Cooling damage facility, etc. Many of these have been applied or can be applied to reactors of the TRIGA family or are already installed or under installation to research reactors of other types. (authors)

  10. Investigation of material removal rate (MRR) and wire wear ratio (WWR) for alloy Ti6Al4 V exposed to heat treatment processing in WEDM and optimization of parameters using Grey relational analysis

    International Nuclear Information System (INIS)

    Altug, Mehmet

    2016-01-01

    The study examines the changes of the microstructural, mechanical and conductivity characteristics of the titanium alloy Ti6Al4 V as a result of heat treatment using wire electrical discharge machining, and their effect on machinability. By means of optical microscopy and scanning electron microscopy (SEM), analyses have been performed to determine various characteristics and additionally, microhardness and conductivity measurements have been conducted. Material removal rate (MRR) and wire wear ratio (WWR) values have been determined by using L18 Taguchi test design. The microstructures of the samples have been changed by thermal procedures. Results have been obtained by using the Grey relational analysis (GRA) optimization technique to solve the maximum MRR and minimum WWR values. The best (highest) MRR value is obtained from sample E which was water quenched in dual phase processing. The microstructure of this sample is composed of primary α and α' phases. The best (lowest) WWR value is obtained from sample A.

  11. Investigation of material removal rate (MRR) and wire wear ratio (WWR) for alloy Ti6Al4 V exposed to heat treatment processing in WEDM and optimization of parameters using Grey relational analysis

    Energy Technology Data Exchange (ETDEWEB)

    Altug, Mehmet [Inonu Univ., Malatya (Turkey). Dept. of Machine and Metal Technologies

    2016-11-01

    The study examines the changes of the microstructural, mechanical and conductivity characteristics of the titanium alloy Ti6Al4 V as a result of heat treatment using wire electrical discharge machining, and their effect on machinability. By means of optical microscopy and scanning electron microscopy (SEM), analyses have been performed to determine various characteristics and additionally, microhardness and conductivity measurements have been conducted. Material removal rate (MRR) and wire wear ratio (WWR) values have been determined by using L18 Taguchi test design. The microstructures of the samples have been changed by thermal procedures. Results have been obtained by using the Grey relational analysis (GRA) optimization technique to solve the maximum MRR and minimum WWR values. The best (highest) MRR value is obtained from sample E which was water quenched in dual phase processing. The microstructure of this sample is composed of primary α and α' phases. The best (lowest) WWR value is obtained from sample A.

  12. Development and validation of a lead emission inventory for the Greater Cairo area

    Directory of Open Access Journals (Sweden)

    Zeinab Safar

    2014-09-01

    Full Text Available Studies that investigate the environmental health risks to Cairo residents invariably conclude that lead is one of the area’s major health hazards. The Cairo Air Improvement Project (CAIP, which was implemented by a team led by Chemonics International, funded by USAID in partnership with the Egyptian Environmental Affairs Agency (EEAA, started developing a lead emission inventory for the greater Cairo (GC area in 1998. The inventory contains a list by major source of the annual lead emissions in the GC area. Uses of the inventory and associated database include developing effective regulatory and control strategies, assessing emissions trends, and conducting modeling exercises. This paper describes the development of the current lead emissions inventory (1999–2010, along with an approach to develop site specific emission factors and measurements to validate the inventory. This paper discusses the major sources of lead in the GC area, which include lead smelters, Mazout (heavy fuel oil combustion, lead manufacturing batteries factories, copper foundries, and cement factories. Included will be the trend in the lead emissions inventory with regard to the production capacity of each source category. In addition, the lead ambient measurements from 1999 through 2010 are described and compared with the results of Source Attribution Studies (SAS conducted in 1999, 2002, and 2010. Due to EEAA/CAIP efforts, a remarkable decrease in more than 90% in lead emissions was attained for 2007.

  13. Experience of work with radioactive materials and nuclear fuel at the reactor WWR-K

    International Nuclear Information System (INIS)

    Maltseva, R.M.; Petukhov, V.K.

    1998-01-01

    In the report there are considered questions concerning the handling with fresh and spent fuel, experimental devices, containing high enriched uranium, being fissile materials of the bulk form, radioisotopes, obtained in the reactor, and radioactive waste, formed during the operation of the reactor, and organization of storage, account and control of radioactive and fissile materials is described. (author)

  14. International Agendas and Local Manifestations: Universities in Cairo, Beirut and Jerusalem after World War I

    Science.gov (United States)

    Huber, Valeska

    2015-01-01

    This article traces the influence of international networks in three Middle Eastern universities from the 1920s onwards: the American University of Beirut, the American University in Cairo and the Hebrew University in Jerusalem. It shows how American, internationalist, imperial and religious actors competed and how the universities were placed in…

  15. Research of heat releasing element of an active zone of gaseous nuclear reactor with pumped through nuclear fuel - uranium hexafluoride (UF6)

    International Nuclear Information System (INIS)

    Batyrbekov, G.; Batyrbekov, E.; Belyakova, E.; Kunakov, S.; Koltyshev, S.

    1996-01-01

    The purpose of the offered project is learning physics and substantiation of possibility of creation gaseous nuclear reactor with pumped through nuclear fuel-hexafluoride of uranium (Uf6).Main problems of this work are'. Determination of physic-chemical, spectral and optical properties of non-equilibrium nuclear - excited plasma of hexafluoride of uranium and its mixtures with other gases. Research of gas dynamics of laminar, non-mixing two-layer current of gases of hexafluoride of uranium and helium at availability and absence of internal energy release in hexafluoride of uranium with the purpose to determinate a possibility of isolation of hexafluoride of uranium from walls by inert helium. Creation and research of gaseous heat releasing element with pumped through fuel Uf6 in an active zone of research nuclear WWR-K reactor. Objects of a research: Non-equilibrium nuclear - excited plasma of hexafluoride of uranium and its mixtures with other gases. With use of specially created ampoules will come true in-reactor probe and spectral diagnostics of plasma. Calculations of kinetics with the account of main elementary processes proceeding in it, will be carried out. Two-layer non-mixed streams of hexafluoride of uranium and helium at availability and absence of internal energy release. Conditions of obtaining and characteristics of such streams will be investigated. Gaseous heat releasing element with pumped through fuel - Uf6 in an active zone of nuclear WWR-K reactor

  16. Prevalence of stuttering in primary school children in Cairo-Egypt.

    Science.gov (United States)

    Abou Ella, Mahmoud; Saleh, Marwa; Habil, Ihab; El Sawy, Mohammed; El Assal, Lamia

    2015-01-01

    To determine the prevalence of stuttering among primary school children in Cairo. A cross-sectional design was employed. Using a multi-stage random sample from 10 schools in Cairo, a total of 8765 primary school students were enrolled in the study. The teacher referring method was initially used to detect stuttering students, which was then confirmed by a Speech Language Pathologist (SLP) using Diagnostic and Statistical Manual for Mental Disorders-Fourth Edition (DSM-IV) criteria. Personal data were collected for all students and separate questionnaires were administered to the parents of each stuttering child, inquiring about consanguinity, family history, presence of other disorders and family attitudes towards the child. Prevalence of stuttering among primary school children in Cairo was 1.03%. The prevalence of stuttering showed a declining trend in the older age group. Stuttering was 7-fold more prevalent among left-handed students. Males had a higher prevalence of stuttering, but didn't reach statistical significance. Anxiety was expressed in 25% of the families of affected children. Positive family history was found in 28% of cases, mainly among first-degree relatives. The current study showed a prevalence of stuttering comparable to other areas of the world with some evidence of hereditary background, although lower than that reported by other studies.

  17. Research studies performed using the Cairo Fourier Diffractometer Facility

    International Nuclear Information System (INIS)

    Maayouf, R.M.A.; Ridikas, D.

    2009-12-01

    This report represents the results of the research studies performed using the Cairo Fourier Diffractometer Facility (CFDF), within 10 years after it was installed and put into operation at the beginning of 1996. The main components of the CFDF were supplied by the IAEA according to the technical assistance project EGY/1/022 'Upgrading of Research Reactor Utilization'. The present report is the second published INDC report, while the first one, published at the beginning of 1997, was about the performance of the CFDF and its main characteristic parameters. Plenty of measurements were performed since then, yielding several publications both in local and international scientific periodicals and resulting in 8 M.Sc. and Ph.D. degrees from Egyptian Universities. In addition, a new approach for the analysis of the neutron spectra was implemented using the CFDF. Specially designed interface card with proper software program was applied instead of the reverse time of flight (RTOF) and Finnish made analyzer originally attached to the facility. It has been verified that the new approach can successfully replace the RTOF analyzer, significantly decreasing the time of measurement and saving the reactor's operation time. Besides, a special fault diagnostic system program was developed and tested for caring and handling the possible failures of the CFDF. Moreover, measurements were carried out for the diffraction spectra emitted at different points of one of the samples. The latter was scanned across the neutron beam of the CFDF, for studying the stress after welding; used in industrial applications. (author)

  18. Residual Stress Studies Using the Cairo Fourier Diffractometer Facility

    International Nuclear Information System (INIS)

    Maayouf, R.M.A.; El-Shaer, Y.H.

    2002-01-01

    The present paper deals with residual stress studies using the Cairo Fourier diffractometer facility CFDF. The CFDF is a reverse - time of -flight (RTOF) diffractometer; applies a Fourier chopper. The measurements were performed for copper samples in order to study the residual stress after welding. The maximum modulation of the Fourier chopper during the measurements was 136 khz; leading to a time resolution half-width of about 7 μ s. It has been found from the present measurements that, the resulting diffraction spectra could be successfully used for studying the residual stress; in the wavelength range between 0.7-2.9 A degree at ∼ 0.45 % relative resolution

  19. Statement to commencement ceremony at American University in Cairo (AUC). 9 February 2006, Cairo, Egypt

    Energy Technology Data Exchange (ETDEWEB)

    ElBaradei, M

    2006-02-09

    In its statement to Commencement Ceremony At American University in Cairo (AUC) the Director General of the IAEA reminisced about his life - the twists and turns it had taken, and the lessons he had learned along the way. His messages to the students was to keep thinking and learning, be ready for opportunity when it comes, treat others with the understanding that we are all part of one human family, live your own life, and take joy in it, be proud of your heritage and engage fully in the future of Egypt.

  20. Statement to commencement ceremony at American University in Cairo (AUC). 9 February 2006, Cairo, Egypt

    International Nuclear Information System (INIS)

    ElBaradei, M.

    2006-01-01

    In its statement to Commencement Ceremony At American University in Cairo (AUC) the Director General of the IAEA reminisced about his life - the twists and turns it had taken, and the lessons he had learned along the way. His messages to the students was to keep thinking and learning, be ready for opportunity when it comes, treat others with the understanding that we are all part of one human family, live your own life, and take joy in it, be proud of your heritage and engage fully in the future of Egypt

  1. Characterization of Ancient Egyptian Wall Paintings, the Excavations of Cairo University at Saqqara

    Directory of Open Access Journals (Sweden)

    Hussein MAREY MAHMOUD

    2011-09-01

    Full Text Available The present study aims at characterizing some Egyptian wall paintings discovered during the excavations of Cairo University (since 1988 and recently in 2005 at Saqqara area in the south of Cairo. There, a number of tombs dating back to the 19th dynasty (c.1293–1185 BC were discovered. The walls of these tombs are carved with bass and raised reliefs and painted with different colours. The characterization of the wall paintings was done by means of optical microscopy (OM, scanning electron microscopy (backscattered electron mode, BSE equipped with an energy dispersive X-ray detector (EDS, micro XRF spectrometry (µ-XRF, and X-ray diffraction analysis (XRD. The analysis of the examined samples indicated that the blue pigment is Egyptian blue (Cuprorivaite, the green pigment is Egyptian green, the red pigment is red ochre, and the yellow pigment is a blended layer of yellow ochre and orpiment (As2S3. The results will help in providing an image concerning some painting materials used during the new Kingdom in ancient Egypt

  2. [[The global significance of the Cairo conference: the new program of action of the International Conference on Population and Development

    Science.gov (United States)

    Atoh, M

    1994-10-01

    "The [1994] International Conference on Population and Development was held in Cairo, Egypt.... In this essay I briefly described global population trends and [their] economic and ecological implications, stated the temporal progress from arguments in the three Preparatory Committees toward the achievement of consensus at the end of the Cairo Conference, summarized and commented [on] each chapter of the Programme of Action, clarified the major characteristics of the Cairo document compared to the documents in Bucharest and Mexico City, and finally discussed the effectiveness of the strategy suggested in the Cairo document for addressing population and development issues in the context of sustainability." (SUMMARY IN ENG) excerpt

  3. [International conference on population and development in Cairo].

    Science.gov (United States)

    van Enk, A

    1994-11-05

    The UN Conference on Population and Development was held in Cairo in September 1994, and dealt with a range of sensitive issues that were eventually recorded in an action program. In addition, a sort of shadow conference was also held by various organizations. The precedents of this conference were the conferences held in Bucharest in 1974, which stressed the world crisis and population explosion, and in Mexico in 1984, where the first signs of the slackening of population growth induced less emphasis on family planning programs and more on the status of women. At Cairo again a crisis atmosphere reigned because rapid population growth has not been followed by rapid development. Birth control discussions also focused on ethical and religious norms, human rights, and emancipation problems. Most of all, the sustainability of development programs was stressed. Global decline of mortality combined with a continuing high birth rate has resulted in a population growth of 3% or more. In the course of 40 years the growth was 46% in industrialized countries as compared to 161% in the poorest lands. The total world population has reached 5 billion, of which only 20% live industrial countries. The influence of the AIDS epidemic on the demographic figures is not likely to be as much as anticipated a few years ago. Other problems are demographic aging, population decline (a below replacement fertility rate in Japan, Spain, and Italy), and uncontrolled internal and international migration (refugees in developing countries and flight to major cities). In the next 30 years almost two-thirds of the population of developing countries will be living in shabby, sprawling megacities. In 1989, in preparation for the Cairo conference, an international forum was held in Amsterdam on population. It dealt with the reproductive rights of women, the negative impact of structural readjustment programs on family planning, and the priority of women's education.

  4. "You are the vanguard of Cairo". NGO / Youth Fora.

    Science.gov (United States)

    Clinton, H R

    1999-01-01

    Everyone has a role to play in realizing the goals of the International Conference on Population and Development (ICPD) program of action. The concerns of young people presented at the Youth Forum will hopefully be kept at the forefront of Cairo+5 deliberations. Innumerable women around the world in every country struggle daily to care for and education their children, to gain greater control over their lives, and to contribute to the progress being made in their communities and countries. The nongovernmental organization (NGO) and youth fora of the Cairo+5 proceedings demonstrate that the discussions about global challenges and their solutions are no longer being held and decided upon solely by government officials and policy-makers behind closed doors. Rather, NGOs have finally taken their proper place in the debate, to help ordinary citizens be heard on the critical issues which affect their lives. Efforts must also continue to be made to reach out to young people, as well as fathers, sons, and husbands.

  5. Performance and main characteristic parameters of the Cairo fourier diffractometer facility at the ET-RR-1 reactor

    International Nuclear Information System (INIS)

    Maayouf, R.M.A.; Abdel-Latif, I.; El-Kady, A.; El-Shafey, A.; Khalil, M.; El-Shaer, Y.

    1997-05-01

    This report represents the results of measurements performed recently with the Cairo Fourier diffractometer facility (CFDF). The main components of the CFDF were supplied by the IAEA according to the technical assistance project EGY/1/022. The CFDF performance is assessed and the main parameters are given. The neutron guide system attached to the CFDF provides a thermal neutron flux ∼ 10 6 n/cm 2 .sec at the sample position; free from fast neutrons and gamma rays background. It has been found, from measurements with different powder samples, that such value of the thermal neutron flux is adequate for neutron diffraction measurements, at scattering angle 2θ 90 deg. and D values between 0.7A and 2.5A; with 52% resolution. (author). 26 refs, 10 figs, 2 tabs

  6. Assessment of structural materials inside the reactor pool of the Dalat research reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien; Luong Ba Vien; Nguyen Minh Tuan; Trang Cao Su

    2010-01-01

    Originally the Dalat Nuclear Research Reactor (DNRR) was a 250-kW TRIGA MARK II reactor, started building from early 1960s and achieved the first criticality on February 26, 1963. During the 1982-1984 period, the reactor was reconstructed and upgraded to 500kW, and restarted operation on March 20, 1984. From the original TRIGA reactor, only the pool liner, beam ports, thermal columns, and graphite reflector have been remained. The structural materials of pool liner and other components of TRIGA were made of aluminum alloy 6061 and aluminum cladding fuel assemblies. Some other parts, such as reactor core, irradiation rotary rack around the core, vertical irradiation facilities, etc. were replaced by the former Soviet Union's design with structural materials of aluminum alloy CAV-1. WWR-M2 fuel assemblies of U-Al alloy 36% and 19.75% 235 U enrichment and aluminum cladding have been used. In its original version, the reactor was setting upon an all-welded aluminum frame supported by four legs attached to the bottom of the pool. After the modification made, the new core is now suspended from the top of the pool liner by means of three aluminum concentric cylindrical shells. The upper one has a diameter of 1.9m, a length of 3.5m and a thickness of 10mm. This shell prevents from any visual access to the upper part of the pool liner, but is provided with some holes to facilitate water circulation in the 4cm gap between itself and the reactor pool liner. The lower cylindrical shells act as an extracting well for water circulation. As reactor has been operated at low power of 500 kW, it was no any problem with degradation of core structural materials due to neutron irradiation and thermal heat, but there are some ageing issues with aluminum liner and other structures (for example, corrosion of tightening-up steel bolt in the fourth beam port and flood of neutron detector housing) inside the reactor pool. In this report, the authors give an overview and assessment of

  7. Main results and status of the development of LEU fuel for Russian research reactors

    International Nuclear Information System (INIS)

    Vatulin, A.; Morozov, A.; Suprun, V.; Dobrikova, I.

    2005-01-01

    VNIINM develops low enrichment uranium (LEU) fuel on base U-Mo alloys and a novel design of pin-type fuel elements. The development is carried out both for existing reactors, and for new advanced designs of reactors. The work is carried on the following main directions: - irradiate LEU U-Mo dispersion fuel (the uranium density up to 6,0 g/cm 3 ) in two Russian research reactors: MIR (RIAR, Dimitrovgrad) as pin type fuel mini-elements and in WWR-M (PINP, Gatchina) within full-scaled fuel assembly (FA) with pin type fuel elements; - finalize development of design and fabrication process of IRT type FA with pin type fuel elements; - develop methods of reducing of U-Mo fuel --Al matrix interaction under irradiation; - develop fabricating methods of fuel elements on base of monolithic U-Mo fuel. The paper generally reviews the results of calculation, design and technology investigations accomplished by now. (author)

  8. Effect of solar radiation on surface ozone in Cairo

    Energy Technology Data Exchange (ETDEWEB)

    Rizk, H F.S. [National Research Centre, Air Pollution Research Dept., Cairo (Egypt)

    1992-04-01

    Measurements of surface ozone content over an urban area in Cairo were conducted during a year, May 1989 to April 1990, while solar radiation at the same area was measured. Low and high concentrations of ozone are compared with those recommended by the WHO expert committee regarding the daily cycle of ozone concentration. 15 refs.

  9. Intermediate evaluation of USAID/Cairo energy policy planning project

    Energy Technology Data Exchange (ETDEWEB)

    Wilbanks, T.J.; Wright, S.B. (Oak Ridge National Lab., TN (United States)); Barron, W.F. (Hong Kong Univ. (Hong Kong)); Kamel, A.M. (Ain Shams Univ., Cairo (Egypt)); Santiago, H.T. (USDOE, Washington, DC (United States))

    1992-01-01

    Three years ago, a team from the Oak Ridge National Laboratory and the Oak Ridge Associated Universities, supplemented by an expert from the US Department of Energy and a senior Egyptian energy professional, carried out what was termed an intermediate evaluation'' of a major energy policy project in Egypt. Supported by USAID/Cairo, the project had concentrated on developing and strengthening an Organization for Energy Planning (OEP) within the Government of India, and it was actually scheduled to end less than a year after this evaluation. The evaluation was submitted to USAID/Cairo and circulated elsewhere in the US Agency for International Development and the Government of Egypt as an internal report. Over the next several years, the USAID energy planning project ended and the functions performed by OEP were merged with planning capabilities in the electric power sector. Now that the major issues addressed by the evaluation report have been resolved, we are making it available to a broader audience as a contribution to the general literature on development project evaluation and institution-building.

  10. Intermediate evaluation of USAID/Cairo energy policy planning project

    Energy Technology Data Exchange (ETDEWEB)

    Wilbanks, T.J.; Wright, S.B. [Oak Ridge National Lab., TN (United States); Barron, W.F. [Hong Kong Univ. (Hong Kong); Kamel, A.M. [Ain Shams Univ., Cairo (Egypt); Santiago, H.T. [USDOE, Washington, DC (United States)

    1992-09-01

    Three years ago, a team from the Oak Ridge National Laboratory and the Oak Ridge Associated Universities, supplemented by an expert from the US Department of Energy and a senior Egyptian energy professional, carried out what was termed an ``intermediate evaluation`` of a major energy policy project in Egypt. Supported by USAID/Cairo, the project had concentrated on developing and strengthening an Organization for Energy Planning (OEP) within the Government of India, and it was actually scheduled to end less than a year after this evaluation. The evaluation was submitted to USAID/Cairo and circulated elsewhere in the US Agency for International Development and the Government of Egypt as an internal report. Over the next several years, the USAID energy planning project ended and the functions performed by OEP were merged with planning capabilities in the electric power sector. Now that the major issues addressed by the evaluation report have been resolved, we are making it available to a broader audience as a contribution to the general literature on development project evaluation and institution-building.

  11. Sound preferences of the dense urban environment: Soundscape of Cairo

    Directory of Open Access Journals (Sweden)

    Mostafa Refat Ismail

    2014-03-01

    Analyzing the relative annoyance increase (RAI of the close-ended part, overall positive RAI values for all sound categories reveal how sensitive to noise Cairo residents are. Results further showed that at an RAI value of approximately 27%, sound category perception transforms from positive to negative.

  12. Annual Patterns of Atmospheric Pollutions and Episodes over Cairo Egypt

    Directory of Open Access Journals (Sweden)

    Y. Aboel Fetouh

    2013-01-01

    Full Text Available The Nile Delta major cities, particularly Cairo, experienced stagnant air pollution episodes, known as Black Cloud, every year over the past decade during autumn. Low-elevated thermal inversion layers play a crucial role in intensifying pollution impacts. Carbon monoxide, ozone, atmospheric temperature, water vapor, and methane measurements from the tropospheric emission spectrometer (TES on board the Aura have been used to assess the dominant component below the inversion layer. In this study, time series analysis, autocorrelations, and cross correlations are performed to gain a better understanding of the connections between those parameters and their local effect. Satellite-based data were obtained for the years 2005–2010. The parameters mentioned were investigated throughout the whole year in order to study the possible episodes that take place in addition to their change from year to year. Ozone and carbon monoxide were the two major indicators to the most basic episodes that occur over Cairo and the Delta region.

  13. Analyses for inserting fresh LEU fuel assemblies instead of fresh HEU fuel assemblies in the Dalat Nuclear Research Reactor in Vietnam

    International Nuclear Information System (INIS)

    Hanan, N. A.; Deen, J.R.; Matos, J.E.

    2005-01-01

    Analyses were performed by the RERTR Program to replace 36 burned HEU (36%) fuel assemblies in the Dalat Nuclear Research Reactor in Vietnam with either 36 fresh fuel assemblies currently on-hand at the reactor or with LEU fuel assemblies to be procured. The study concludes that the current HEU (36%) WWR-M2 fuel assemblies can be replaced with LEU WWR-M2 fuel assemblies that are fully-qualified and have been commercially available since 2001 from the Novosibirsk Chemical Concentrates Plant in Russia. The current reactor configuration using re-shuffled HEU fuel began in June 2004 and is expected to allow normal operation until around August 2006. If 36 HEU assemblies each with 40.2 g 235 U are inserted without fuel shuffling over the next five operating cycles, the core could operate for an additional 10 years until June 2016. Alternatively, inserting 36 LEU fuel assemblies each containing 49.7 g 235 U without fuel shuffling over five operating cycles would allow normal operation for about 14 years from August 2006 until October 2020. The main reason for the longer service life of the LEU fuel is that its 235 U content is higher than the 235 U content needed simply to match the service life of the HEU fuel. Fast neutron fluxes in the experiment regions would be very nearly the same in both the HEU and LEU cores. Thermal neutron fluxes in the experiment regions would be lower by 1-5%, depending on the experiment type and location. (author)

  14. MODIF-a code for completely reflected cylindrical reactors

    International Nuclear Information System (INIS)

    Gaafar, M.; Mechail, I.; Tadrus, S.

    1981-01-01

    MODIF-Code is a computer program for calculating the reflector saving, material buckling, and effective multiplication constant of completely reflected cylindrical reactors. The calculational method is based on a modified iterative algorithm which has been deduced from the general analytical solution of the two group diffusion equations. The code has been written in FORTRAN language suited for the ICL-1906 computer facility at Cairo University. The computer time required to solve a problem of actual reactor is less than 1 minute. The problem converges within five iteration steps. The accuracy in determining the effective multiplication constant lies within +-10 -5 . The code has been applied to the case of UA-RR-1 reactor, the results confirm the validity and accuracy of the calculational method

  15. Frequent transient hepatitis C viremia without seroconversion among healthcare workers in Cairo, Egypt.

    Directory of Open Access Journals (Sweden)

    Aline Munier

    Full Text Available BACKGROUNDS: With 10% of the general population aged 15-59 years chronically infected with hepatitis C virus (HCV, Egypt is the country with the highest HCV prevalence worldwide. Healthcare workers (HCWs are therefore at particularly high risk of HCV infection. Our aim was to study HCV infection risk after occupational blood exposure among HCWs in Cairo. METHODOLOGY/PRINCIPAL FINDINGS: The study was conducted in 2008-2010 at Ain Shams University Hospital, Cairo. HCWs reporting an occupational blood exposure at screening, having neither anti-HCV antibodies (anti-HCV nor HCV RNA, and exposed to a HCV RNA positive patient, were enrolled in a 6-month prospective cohort with follow-up visits at weeks 2, 4, 8, 12 and 24. During follow-up, anti-HCV, HCV RNA and ALT were tested. Among 597 HCWs who reported a blood exposure, anti-HCV prevalence at screening was 7.2%, not different from that of the general population of Cairo after age-standardization (11.6% and 10.4% respectively, p = 0.62. The proportion of HCV viremia among index patients was 37%. Of 73 HCWs exposed to HCV RNA from index patients, nine (12.3%; 95%CI, 5.8-22.1% presented transient viremia, the majority of which occurred within the first two weeks after exposure. None of the workers presented seroconversion or elevation of ALT. CONCLUSIONS/SIGNIFICANCE: HCWs of a general University hospital in Cairo were exposed to a highly viremic patient population. They experienced frequent occupational blood exposures, particularly in early stages of training. These exposures resulted in transient viremic episodes without established infection. These findings call for further investigation of potential immune protection against HCV persistence in this high risk group.

  16. Frequent Transient Hepatitis C viremia without Seroconversion among Healthcare Workers in Cairo, Egypt

    Science.gov (United States)

    Munier, Aline; Marzouk, Diaa; Abravanel, Florence; El-Daly, Mai; Taylor, Sylvia; Mamdouh, Rasha; Eldin, Waleed Salah; El-Arab, Hanan Ezz; Sos, Dalia Gaber; Momen, Mohamed; Okasha, Omar; Le Fouler, Lenaig; El-Hosini, Mostafa; Izopet, Jacques; Rafik, Mona; Albert, Matthew; Abdel-Hamid, Mohamed; Mohamed, Mostafa Kamal; Delarocque-Astagneau, Elisabeth; Fontanet, Arnaud

    2013-01-01

    Backgrounds With 10% of the general population aged 15–59 years chronically infected with hepatitis C virus (HCV), Egypt is the country with the highest HCV prevalence worldwide. Healthcare workers (HCWs) are therefore at particularly high risk of HCV infection. Our aim was to study HCV infection risk after occupational blood exposure among HCWs in Cairo. Methodology/Principal Findings The study was conducted in 2008–2010 at Ain Shams University Hospital, Cairo. HCWs reporting an occupational blood exposure at screening, having neither anti-HCV antibodies (anti-HCV) nor HCV RNA, and exposed to a HCV RNA positive patient, were enrolled in a 6-month prospective cohort with follow-up visits at weeks 2, 4, 8, 12 and 24. During follow-up, anti-HCV, HCV RNA and ALT were tested. Among 597 HCWs who reported a blood exposure, anti-HCV prevalence at screening was 7.2%, not different from that of the general population of Cairo after age-standardization (11.6% and 10.4% respectively, p = 0.62). The proportion of HCV viremia among index patients was 37%. Of 73 HCWs exposed to HCV RNA from index patients, nine (12.3%; 95%CI, 5.8–22.1%) presented transient viremia, the majority of which occurred within the first two weeks after exposure. None of the workers presented seroconversion or elevation of ALT. Conclusions/Significance HCWs of a general University hospital in Cairo were exposed to a highly viremic patient population. They experienced frequent occupational blood exposures, particularly in early stages of training. These exposures resulted in transient viremic episodes without established infection. These findings call for further investigation of potential immune protection against HCV persistence in this high risk group. PMID:23469082

  17. U.S. and foreign breeder reactors

    International Nuclear Information System (INIS)

    Hill, E.H.

    1977-01-01

    The running battle between Congress and the Administration over the Clinch River Breeder Reactor Plant (CRBRP) Project has provoked an increased interest in domestic and foreign breeder reactor programs. Perhaps an understanding of the history of breeders here and abroad will serve to place the CRBRP in perspective and allow some analysis of how the U.S. appears on the global canvas. Breeder reactor technology has, for the most part, settled down to concentration on the liquid metal fast breeder reactor (LMFBR). This is the result of 32 years of experience with reactors employing a fast neutron flux and even longer experience with liquid metal coolants. However, a number of U.S. utilities are sponsoring a gas cooled fast reactor program as an alternative technology to the LMFBR. This development program is supported by the U.S. Department of Energy

  18. Test reactor: basic to U.S. breeder reactor development

    International Nuclear Information System (INIS)

    Miller, B.J.; Harness, A.J.

    1975-01-01

    Long-range energy planning in the U. S. includes development of a national commercial breeder reactor program. U. S. development of the LMFBR is following a conservative sequence of extensive technology development through use of test reactors and demonstration plants prior to construction of commercial plants. Because materials and fuel technology development is considered the first vital step in this sequence, initial U. S. efforts have been directed to the design and construction of a unique test reactor. The Fast Flux Test Facility, FFTF, is a 400 MW(t) reactor with driver fuel locations, open test locations, and closed loops for higher risk experiments. The FFTF will provide a prototypic LMFBR core environment with sufficient instrumentation for detailed core environmental characterization and a testing capability substituted for breeder capability. The unique comprehensive fuel and materials testing capability of the FFTF will be key to achieving long-range objectives of increased power density, improved breeding gain and shorter doubling times. (auth)

  19. A study of ultraviolet solar radiation at Cairo urban area, Egypt

    Energy Technology Data Exchange (ETDEWEB)

    Robaa, S.M. [Cairo Univ., Giza (Egypt). Dept. of Astronomy and Meterology

    2004-07-01

    The monthly mean values of global, G, and ultraviolet, UV, solar radiation incident on a horizontal surface at Cairo urban area during the two different periods (1969-1973) and (1993-1997) are presented, analyzed and compared. The effect of urbanization processes on the solar radiation components is investigated and discussed. It was found that the total radiation of the two components, G and UV received at the urban area of Cairo during the period (1969-1973) highly exceeds the radiation received during the period (1993-1997) for all months of the year. The mean relative reduction of G and UV reached 17.4% and 27.4% respectively. A significant correlation between G and UV radiation has been established and the recommended correlation equation has been stated to estimate the values of UV radiation that are difficult to measure at any site in the zone of Lower Egypt. Also, a comparative study of the two radiation components, G and UV, at urban (Cairo) and rural (Bahtim) areas during the period (1993-1997) revealed that the urban area always has values of G and UV radiation distinctly lower than that found in rural area for all months of the year. Urban-rural mean reduction of G and UV reached 7.0% and 17.9% respectively. The ratio of the ultraviolet to global radiation (UV/G) are calculated and compared with other sites in the Arabian Peninsula. The effect of atmospheric dust on the measured solar radiation components is also investigated and discussed. (author)

  20. The modification of the Rossendorf Research Reactor

    International Nuclear Information System (INIS)

    Gehre, G.; Hieronymus, W.; Kampf, T.; Ringel, V.; Robbander, W.

    1990-01-01

    The Rossendorf Research Reactor is of the WWR-SM type. It is a heterogeneous water moderated and cooled tank reactor with a thermal power of 10 MW, which was in operation from 1957 to 1986. It was shut down in 1987 for comprehensive modifications to increase its safety and to improve the efficiency of irradiation and experimentals. The modifications will be implemented in two steps. The first one to be finished in 1989 comprises: 1) the replacement of the reactor tank and its components, the reactor cooling system, the ventilation system and the electric power installation; 2) the construction of a new reactor control room and of filtering equipment; 3) the renewal of process instrumentation and control engineering equipment for reactor operation, equipment for radiation protection monitoring, and reactor operation and safety documentation. The second step, to be implemented in the nineties, is to comprise: 1) the enlargement of the capacity for storage of spent fuel; 2) the modernization of reactor operations by computer-aided control; 3) the installation of an automated measuring systems for accident and environmental monitoring. Two objects of the modification, the replacement of the reactor tank and the design of a new and safer one as well as the increase of the redundancy of the core emergency cooling system are described in detail. For the tank replacement the exposure data are also given. Furthermore, the licensing procedures based on national ordinances and standards as well as on international standards and recommendations and the mutual responsibilities and activities of the licensing authority and of the reactor manager are presented. Finally, the present state of the modifications and the schedule up to the reactor recommissioning and test operation at full power is outlined

  1. Code-Switching in Judaeo-Arabic Documents from the Cairo Geniza

    Science.gov (United States)

    Wagner, Esther-Miriam; Connolly, Magdalen

    2018-01-01

    This paper investigates code-switching and script-switching in medieval documents from the Cairo Geniza, written in Judaeo-Arabic (Arabic in Hebrew script), Hebrew, Arabic and Aramaic. Legal documents regularly show a macaronic style of Judaeo-Arabic, Aramaic and Hebrew, while in letters code-switching from Judaeo-Arabic to Hebrew is tied in with…

  2. Profile of genetic disorders prevalent in northeast region of Cairo ...

    African Journals Online (AJOL)

    As clinical geneticists, we recently reviewed our 43 years experience in an attempt to represent the frequency of genetic disorders in the Division of Genetics at Pediatric Hospital, Faculty of Medicine, Ain-Shams University, Cairo, Egypt, during the period from 1966 to 2009. All patients (from birth up to 18 years) suspected of ...

  3. Virtual microscopy beyond the pyramids, applications of WSI in Cairo University for E-education & telepathology.

    Science.gov (United States)

    Ayad, Essam; Yagi, Yukako

    2012-01-01

    Telepathology, the practice of pathology at a long distance, has advanced continuously since 1986. The progress of telepathology passed through four stages: Static, Dynamic, Hybrid & Whole Slide Imaging. A pilot project between the Italian Hospital in Cairo & the Civico Hospital in Palermo was completed successfully, applying the static & dynamic techniques of telepathology. This project began in 2003 and continued till now. In 2004, centers in Venice, London and Pittsburgh participated actively in our project. Over eight years we consulted on many problematic pathological cases with specialized pathological centers in Italy, U.K. & U.S.A. In addition to the highly specialized scientific value, we saved a lot of time and money. We concluded from our experience that telepathology is a very useful and applicable tool for additional consulting on difficult pathological cases especially for emerging countries. In view of this success we have already established our Digital Telepathology Unit in Cairo University, using the WSI technique in teaching which was greatly successful and encouraged us to build a huge digital pathology library which will expand our telepathology & E-learning programs to cover staff and students in Egypt and Eastern Mediterranean.

  4. Irradiation test plan of oxidation-resistant graphite in WWR-K Research Reactor

    International Nuclear Information System (INIS)

    Sumita, Junya; Shibata, Taiju; Sakaba, Nariaki; Osaki, Hirotaka; Kato, Hideki; Fujitsuka, Kunihiro; Muto, Takenori; Gizatulin, Shamil; Shaimerdenov, Asset; Dyussambayev, Daulet; Chakrov, Petr

    2014-01-01

    Graphite materials are used for the in-core components of High Temperature Gas-cooled Reactor (HTGR) which is a graphite-moderated and helium gas-cooled reactor. In the case of air ingress accident in HTGR, SiO_2 protective layer is formed on the surface of SiC layer in TRISO CFP and oxidation of SiC does not proceed and fission products are retained inside the fuel particle. A new safety concept for the HTGR, called Naturally Safe HTGR, has been recently proposed. To enhance the safety of Naturally Safe HTGR ultimately, it is expected that oxidation-resistant graphite is used for graphite components to prevent the TRISO CFPs and fuel compacts from failure. SiC coating is one of candidate methods for oxidation-resistant graphite. JAEA and four graphite companies launched R&Ds to develop the oxidation-resistant graphite and the International Science and Technology Center (ISTC) partner project with JAEA and INP was launched to investigate the irradiation effects on the oxidation-resistant graphite. To determine grades of the oxidation-resistant graphite which will be adopted as irradiation test, a preliminary oxidation test was carried out. This paper described the results of the preliminary oxidation test, the plan of out-of-pile test, irradiation test and post-irradiation test (PIE) of the oxidation-resistant graphite. The results of the preliminary oxidation test showed that the integrity of the oxidation resistant graphite was confirmed and that all of grades used in the preliminary test can be adopted as the irradiation test. Target irradiation temperature was determined to be 1473 (K) and neutron fluence was determined to be from 0.54 × 10"2"5through 1.4 × 10"2"5 (/m"2, E>0.18MeV). Weight change, oxidation rate, activation energy, surface condition, etc. will be evaluated in out-of-pile test and weight change, irradiation effect on oxidation rate and activation energy, surface condition, etc. will be evaluated in PIE. (author)

  5. Cairo city air quality research initiative part-i: A meteorological modelling

    International Nuclear Information System (INIS)

    Abdel-AAl, M.M.

    2001-01-01

    The modified meteorological model Hotmac (Higher order turbulence model for atmospheric circulation) is a three-dimensional and finite grid model developed primarily for simospheric motions and based on solving the conservation equations of mass momentum, energy and turbulent kinetic energy. The model is used for studying air quality of cairo cty and its surrounding to treat a domain that includes an urbanized area for understanding problems of air pollution. The acquired terrain (elevation) data for Egypt was obtained. The local and upper level geostrophic data were provided by rawinsonde of wind speed and direction, temperature,relative humidity, water vapour, and pressure The potential temperature was obtained by a computer program. The meteorological data was obtained for helwan site, about 20 kilometer south of cairo city. Three mested grids were used, with grids resolutions of 2 6 and 18 kilometers to cover a domain of approximately 360 km that extended from the red Sea to the mediterranean Sea

  6. The Vatican at the United Nations. Cairo + 5.

    Science.gov (United States)

    Kissling, F

    1999-01-01

    During the International Conference on Population and Development in Cairo, a remarkable consensus on population and development was forged and a Programme of Action was issued. With its permanent observer status among governments at the UN, the Vatican had attempted to block such a worldwide consensus on a new structure for population and development programs, based on women's empowerment, universal and voluntary access to contraception, and improved reproductive health for all. After 5 years of implementing the Cairo Programme of Action, the UN conducted a review and appraisal of its implementation, ending with a final preparatory meeting and a Special Session of the UN General Assembly. During the review process and the meeting, the Vatican remained active but fell short, on the whole, of thwarting progress. The Vatican delegation was made up of five individuals--two women and three men, including two priests. Almost all their interventions were focused on the goal of obstructing progressive understanding of what would be necessary if the Programme of Action were to be fully and fairly implemented. This included the provision of emergency contraception to refugees; the definition of human rights; addressing unsafe abortion as a major public health issue; the provision of condoms for protection against HIV/AIDS; adolescent rights to privacy and confidentiality; and the inclusion of sex education in school curricula.

  7. Experiences of activity measurements of primary circuit materials in a WWR-SM research reactor

    International Nuclear Information System (INIS)

    Elek, A.; Toth, M.; Bakos, L.; Vizdos, G.

    1980-01-01

    The activity of water and gas samples taken from the primary circuit have been measured nondestructively for more than two years to monitor the technological parameters of the reactor. In the primary water samples 17 fission products and seven activated traces, as well as six radioactive conponents in the gas samples were determined routinely by Ge/Li gamma-spectrometry. (author)

  8. U.S. Domestic Reactor Conversion Programs

    International Nuclear Information System (INIS)

    Woolstenhulme, Eric

    2008-01-01

    The Conversion Projects Include: the revision of the facilities safety basis documents and supporting analysis, the fabrication of new LEU fuel, the change-out of the reactor core, and the removal of the used HEU fuel (by INL University Fuels Program or DOE-NE). The major entities involved are: the U.S. Nuclear Regulatory Commission, the University reactor department, the fuel and hardware fabricators, the Spent fuel receipt facilities, the Spent fuel shipping services, and the U.S. Department of Energy and their subcontractors. Three major Reactor Conversion Program milestones have been accomplished since 2006: the conversion of the TRIGA reactor at Texas A and M University Nuclear Science Center, the conversion of the University of Florida Training Reactor, and the conversion of the Purdue University Reactor. Four Reactor Conversion Program milestones yet to be accomplished in 2008 and 2009: the Washington State University Nuclear Radiation Center reactor, the Oregon State University TRIGA Reactor, the University of Wisconsin Nuclear Reactor, and the Neutron Radiography Reactor Facility. NNSA is committed to doing things cheaper, better, smarter, safer through a 'Lessons Learned' process. The conversion team assessed each major activity grouping: Project Initiation, Conversion Proposal Development, Fuel Fabrication and Hardware, Core Conversion, and Spent Nuclear Fuel Removal. Issues were identified and recommendations were given

  9. Burnable absorber for the PIK reactor

    International Nuclear Information System (INIS)

    Gostev, V.V.; Smolskii, S.L.; Tchmshkyan, D.V.; Zakharov, A.S.; Zvezdkin, V.S.; Konoplev, K.A.

    1998-01-01

    In the reactor PIK design a burnable absorber is not used and the cycle duration is limited by the rods weight. Designed cycle time is two weeks and seams to be not enough for the 100 MW power research reactor equipped by many neutron beams and experimental facilities. Relatively frequent reloading reduces the reactor time on full power and in this way increases the maintenance expenses. In the reactor core fuel elements well mastered by practice are used and its modification was not approved. We try to find the possibilities of installation in the core separate burnable elements to avoid poison of the fuel. It is possible to replace a part of the fuel elements by absorbers, since the fuel elements are relatively small (diameter 5.15mm, uranium 235 content 7.14g) and there are more then 3800 elements in the core. Nevertheless, replacing decreases the fuel burnup and its consumption. In the PIK fuel assembles a little part of the volume is occupied by the dumb elements to create a complete package of the assembles shroud, that is necessary in the hydraulic reasons. In the presented report the assessment of such a replacement is done. As a burnable material Gadolinium was selected. The measurements or the beginning of cycle were performed on the critical facility PIK. The burning calculation was confirmed by measurements on the 18MW reactor WWR-M. The results give the opportunity to twice the cycle duration. The proposed modification of the fuel assembles does not lead to alteration in the other reactor systems, but it touch the burned fuel reprocessing technology. (author)

  10. Informal Urban Development in Cairo

    DEFF Research Database (Denmark)

    Steinø, Nicolai; Petersen, Mads Dines

    2017-01-01

    The city of Cairo, Egypt, currently experiences rapid urban growth. Large parts of the city expand without formal urban planning. This results in large-scale informal and unplanned development. In addition, the resulting urban fabric and individual buildings feature severe deficiencies when...... it comes to the basic quality of urban space, ventilation and daylight. While retrofitting already built-up areas would be a huge challenge, some minor improvements might be possible in future development even within the current mode of production of these spaces. In recent years, parametric design tools...... have opened up new possibilities for modelling in urban design. By way of a parametric design approach, different urban design parameters can be modified and new urban space scenarios can be rendered three dimensionally in almost real time. In short, this is parametric urban design. It opens up...

  11. Analysis of pollutants in human scalp hair in Cairo

    International Nuclear Information System (INIS)

    Abdel-Wahab, M.F.; Abdulla, W.A.; Rashid, S.M.; Yousef, A.

    1985-01-01

    Scalp hair, urine and blood samples from volunteers selected from different areas surrounding Cairo were collected for study by neutron activation analysis (NAA) and conventional methods. The results for 14 elements in hair show some variation between the different regions. Qualitatively there is a slight difference of abundance of the investigated elements. Broadly speaking the presence of major elements is dominant. No relationship was observed between the elemental composition of hair and urine. (author)

  12. Recent U.S. reactor operating experience

    International Nuclear Information System (INIS)

    Stello, V. Jr.

    1977-01-01

    A qualitative assessment of U.S. and foreign reactor operating experience is provided. Recent operating occurrences having potentially significant safety impacts on power operation are described. An evaluation of the seriousness of each of these issues and the plans for resolution is discussed. A quantitative report on U.S. reactor operational experience is included. The details of the NRC program for evaluating and applying operating reactor experience in the regulatory process is discussed. A review is made of the adequacy of operating reactor safety and environmental margins based on actual operating experience. The Regulatory response philosophy to operating reactor experiences is detailed. This discussion indicates the NRC emphasis on the importance of a balanced action plan to provide for the protection of public safety in the national interest

  13. Current status of operation and utilization of the Dalat research reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien; Le Van So

    2004-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW swimming pool type reactor using the Soviet WWR-SM fuel assembly with 36% enrichment of U-235. It was upgraded from the USA 250 kW TRIGA Mark-II reactor. The first criticality of the renovated reactor was in November 1983 and its regular operation at nominal power of 500 kW has been since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs, once every 4 weeks, for radioisotope production, neutron activation analyses and research purposes. The remaining time between two continuous runs is devoted to maintenance activities and also to short run for physics experiments and training purpose. From the first start-up to the end of December 2002, it totaled about 24,700 hrs of operation and the total energy released was 490 MWd. After 10 years of operation with the core of 89-fuel assembly configuration, in April 1994, the first refueling work was done and the 100-fuel assembly configuration was set-up. The second fuel reloading was executed in March 2002. At present time, the working configuration of the reactor core consists of 104 fuel assemblies. This fuel reloading will ensure efficient exploitation of the reactor for about 3 years with 1200-1300 hrs per year at nominal power. The current status of operation and utilization and some activities related to the reactor core management of the DNRR are presented and discussed in this paper. (author)

  14. Toward Reform of Egyptian Higher Education: Final Report on Cairo University/Boston University Collaboration in Counterpart Training for the Third Education Project.

    Science.gov (United States)

    Shann, Mary H.; Cronin, Joseph M.

    In 1981, the Egyptian government sought assistance from the World Bank's International Developmental Agency for the Cairo Univesity-IDA Third Education Project. The World Bank loan was designated for training faculty leaders capable of modernizing instruction at Cairo University and for equipping the faculties of agriculture and medicine with…

  15. Simulation of atmospheric temperature inversions over greater cairo using the MM5 Meso-Scale atmospheric model

    International Nuclear Information System (INIS)

    Kandil, H.A.; Elhadidi, B.M.; Kader, A. A.; Moaty, A.A.; Sherif, A.O.

    2006-01-01

    Air pollution episodes have been recorded in Cairo, during the fall season, since 1999, as a result of specific meteorological conditions combined with large quantity of pollutants created by several ground-based sources. The main reason for the smog-like episodes (black clouds) is adverse weather conditions with low and variable winds, high humidity and strong temperature inversions in the few-hundred meters above the ground. The two important types of temperature inversion affecting the air pollution are surface or ground (radiation) inversion and subsidence (elevated) inversion. The surface temperature inversion is associated with a rapid decrease in the ground surface temperature with the simultaneous existence of warm air in the lower troposphere. The inversion develops at dusk and continues until the surface warms again the following day. Pollutants emitted during the night are caught under this i nversion lid. S ubsidence inversion forms when warm air masses move over colder air masses. The inversion develops with a stagnating high-pressure system (generally associated with fair weather). Under these conditions, the pressure gradient becomes progressively weaker so that winds become light. These light winds greatly reduce the horizontal transport and dispersion of pollutants. At the same time, the subsidence inversion acts as a barrier to the vertical dispersion of the pollutants. In this study, the Penn State/NCAR meso -scale model (MM5) is used to simulate the temperature inversion phenomenon over Greater Cairo region during the fall season of 2004. Accurate computations of the heat transfer at the surface are needed to capture this phenomenon. This can only be achieved by high-resolution simulations in both horizontal and vertical directions. Hence, for accurate simulation of the temperature inversion over Greater Cairo, four nested domains of resolutions of 27 km, 9 km, 3 km and 1 km, respectively, were used in the horizontal planes. Furthermore, 42

  16. The determination of fast neutron fluence in radiation stability tests of steel samples

    International Nuclear Information System (INIS)

    Hogel, J.; Vespalec, R.

    1979-01-01

    The activation method is described of determining fast neutron fluence. Samples of steel designed for WWER type reactor pressure vessels were irradiated in the CHOUCA-rigs in the core of the WWR-S reactor. The neutron spectrum was measured by the multiple activation foil method and the effective cross sections of fluence monitors were calculated. The fluences obtained from the reactions 54 Fe(n,p) 54 Mn and 63 Cu(n,α) 60 Co are presented and the method is discussed. (author)

  17. Structural Study and Evaluation of Previous Restoration Work of Mohammad 'Ali Pasha Mosque at the Citadel in Cairo

    Directory of Open Access Journals (Sweden)

    dr.Yaser Yehya Amin Abdel-Aty

    2011-01-01

    Full Text Available Mohammad 'Ali Pasha Mosque at the Citadel in Cairo is considered one of the main landmarks in Egypt. It majestically stands at a northwestern bend of the Citadel and it is visible from numerous locations in Cairo. It has become the symbol of the Citadel, to the point that its name is given to the whole complex in the colloquial Egyptian parlance. This paper studies analytically the static and dynamic structural behavior of this great mosque using computer numerical modeling techniques, to reach the main reasons for past cracking and failures in its domed-roof and other structural elements, which occurred by the end of 19th Century. A number of 3D-models are analyzed to study the mosque, in both original and after restoration conditions, under static (i.e. dead and live loads and dynamic (i.e. Eigenvector modal analysis, response-spectrum and time-history cases of loading. Besides, structural evaluation of major restoration project, in 1930s, is conducted to determine the current structural safety status of the mosque

  18. Current status and ageing management of the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen Nhi Dien [Nuclear Research Institute, Dalat (Viet Nam)

    2000-10-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW swimming pool type reactor loaded with the Soviet WWR-M2 fuel elements, moderated and cooled by light water. It was reconstructed and upgraded from the former 250 kW TRIGA Mark-II reactor built in 1963. The first criticality of the renovated reactor was in November 1983 and it has been put in regular operation at nominal power since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs every 4 weeks, for radioisotope production, neutron activation analyses and other research purposes. The remaining time is devoted to maintenance work and to short runs for reactor physics studies as well. From its first start-up to the end of 1998, it totaled about 20,000 hrs of operation at nominal power. After ten years of operation, reactor general inspection and refurbishment were implemented in the 1992-1996 period. In April 1994, refueling work was executed with adding of 11 fresh fuel elements to the reactor core. At present, the reactor has been working with 100-fuel element configuration. Corrosion study has been implemented by visual inspection of the reactor pool tank and some other inside components which remain unchanged from the previous TRIGA reactor. The inspections were carried out with the assistance of some experts from other countries. Some visual inspection results have been obtained and the nature of the electrochemical corrosion and related aspects were little by little identified. In this paper, the operation status of the Dalat reactor is presented, and some activities related to the ageing management of the reactor pool tank and its inside components are also discussed. (author)

  19. Current status and ageing management of the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien

    2000-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW swimming pool type reactor loaded with the Soviet WWR-M2 fuel elements, moderated and cooled by light water. It was reconstructed and upgraded from the former 250 kW TRIGA Mark-II reactor built in 1963. The first criticality of the renovated reactor was in November 1983 and it has been put in regular operation at nominal power since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs every 4 weeks, for radioisotope production, neutron activation analyses and other research purposes. The remaining time is devoted to maintenance work and to short runs for reactor physics studies as well. From its first start-up to the end of 1998, it totaled about 20,000 hrs of operation at nominal power. After ten years of operation, reactor general inspection and refurbishment were implemented in the 1992-1996 period. In April 1994, refueling work was executed with adding of 11 fresh fuel elements to the reactor core. At present, the reactor has been working with 100-fuel element configuration. Corrosion study has been implemented by visual inspection of the reactor pool tank and some other inside components which remain unchanged from the previous TRIGA reactor. The inspections were carried out with the assistance of some experts from other countries. Some visual inspection results have been obtained and the nature of the electrochemical corrosion and related aspects were little by little identified. In this paper, the operation status of the Dalat reactor is presented, and some activities related to the ageing management of the reactor pool tank and its inside components are also discussed. (author)

  20. Submersion-Subcritical Safe Space (S4) reactor

    International Nuclear Information System (INIS)

    King, Jeffrey C.; El-Genk, Mohamed S.

    2006-01-01

    The Submersion-Subcritical Safe Space (S 4 ) reactor, developed for future space power applications and avoidance of single point failures, is presented. The S 4 reactor has a Mo-14% Re solid core, loaded with uranium nitride fuel, cooled by He-30% Xe and sized to provide 550 kWth for 7 years of equivalent full power operation. The beryllium oxide reflector of the S 4 reactor is designed to completely disassemble upon impact on water or soil. The potential of using Spectral Shift Absorber (SSA) materials in different forms to ensure that the reactor remains subcritical in the worst-case submersion accident is investigated. Nine potential SSAs are considered in terms of their effect on the thickness of the radial reflector and on the combined mass of the reactor and the radiation shadow shield. The SSA materials are incorporated as a thin (0.1 mm) coating on the outside surface of the reactor core and as core additions in three possible forms: 2.0 mm diameter pins in the interstices of the core block, 0.25 mm thick sleeves around the fuel stacks and/or additions to the uranium nitride fuel. Results show that with a boron carbide coating and 0.25 mm iridium sleeves around the fuel stacks the S 4 reactor has a reflector outer diameter of 43.5 cm with a combined reactor and shadow shield mass of 935.1 kg. The S 4 reactor with 12.5 at.% gadolinium-155 added to the fuel, 2.0 mm diameter gadolinium-155 sesquioxide interstitial pins, and a 0.1 mm thick gadolinium-155 sesquioxide coating has a slightly smaller reflector outer diameter of 43.0 cm, resulting in a smaller total reactor and shield mass of 901.7 kg. With 8.0 at.% europium-151 added to the fuel, along with europium-151 sesquioxide for the pins and coating, the reflector's outer diameter and the total reactor and shield mass are further reduced to 41.5 cm and 869.2 kg, respectively

  1. Measurements of radiological background and some chemical pollutants in two areas of greater cairo

    International Nuclear Information System (INIS)

    Tawfik, F.S.; Ramadan, A.; Abdel Aziz, M.A.; Aly, A.I.M.

    2002-01-01

    The present work aims to the evaluation of radiological background levels and chemical pollutants in greater cairo as the most dense populated city in Egypt. The meteorological data of a complete one year of Cairo city have been collected, investigated and processed to determined the behavior of the pollutants in the atmosphere and the sector that is strongly affected by the pollutants. Portable detector for measuring the radiological background was deployed in Nasr City, where two nuclear centers belonging to Atomic Energy Authority are located, to measure the radioactivity levels in the atmosphere and compare them with the international standard limits. Other detectors were deployed in Shobra El- Khema area to study two significant phenomena, the first is the formation of ozone through the photo-chemical oxidation, its level and its behavior in the atmosphere, taking into consideration the international standard limits. The second phenomenon is the impact of the black plume on the capital Cairo started on October (1999) and its association of pollutant levels increment, defining the nature and the site location of the pollutant source. The carbon monoxide concentrations (as an example), before and during the black plume, were calculated using Gaussian equation then compared with the measured data in Shobra El- Khema region. The other available instruments were used to measure nitrogen oxides, ozone and carbon monoxide

  2. Regeneration as an approach for the development of informal settlements in Cairo metropolitan

    Directory of Open Access Journals (Sweden)

    Ghada Farouk Hassan

    2012-09-01

    Finally the paper ends by discussing the capability of the application of this approach in dealing with the informal settlements in Cairo metropolitan as proper approach to cope with the need of dealing effectively with those shadows in the urban context.

  3. Improving the marketing abilities of some egyptian exports using radiation technology in cairo air port

    International Nuclear Information System (INIS)

    Elgamel, E.A.; ELKateeb, M.A.

    2005-01-01

    The economics of establishing a food irradiation facility at cairo airport are discussed together with the effect of various parameters on uint processing costs. This study comprises the determination of the commodity mix for the egyptian food commodities that are proposed for irradiation and export from the cairo airport. The commodity mix is distributed for the full utilization of the working capacity and the evaluation of the type of the irradiation facility and also the radiation source strength. The financial analysis for such an irradiation facility is also carried out. It provides a model for calculating specific unit processing costs by correlating known capital costs with annual operation cost and annual throughputs. We analyzed the cost- benefit of the proposed food irradiation facility. We took into account the cost of the capital investment, operation and other additional parameters and then estimated the unit cost. The investment criteria utilized for commercial evaluation were internal rate of return (I.I.R.) and pay back period (P.B.P.). The irradiation cost and the additional income are also discussed. The results of this analysis showed that the installation of the an irradiation unit for the establishment of food irradiation unit in cairo air port in would be economically feasible

  4. Research reactor`s role in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Choi, C-O [Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

    1996-12-31

    After a TRIGA MARK-II was constructed in 1962, new research activity of a general nature, utilizing neutrons, prevailed in Korea. Radioisotopes produced from the MARK-II played a good role in the 1960`s in educating people as to what could be achieved by a neutron source. Because the research reactor had implanted neutron science in the country, another TRIGA MARK-III had to be constructed within 10 years after importing the first reactor, due to increased neutron demand from the nuclear community. With the sudden growth of nuclear power, however, the emphasis of research changed. For a while research activities were almost all oriented to nuclear power plant technology. However, the specifics of nuclear power plant technology created a need for a more highly capable research reactor like HANARO 30MWt. HANARO will perform well with irradiation testing and other nuclear programs in the future, including: production of key radioisotopes, doping of silicon by transmutation, neutron activation analysis, neutron beam experiments, cold neutron source. 3 tabs., 2 figs.

  5. [Between Puebla and Cairo Plus Five].

    Science.gov (United States)

    1998-03-01

    The National Forum of Women and Population Policies was held in Puebla, Mexico, in January 1998 to assess achievements and lags in carrying out the Program of Action adopted at the International Conference on Population and Development in Cairo. The forum proposed diagnosing the current situation in order to compare existing realities with proposals contained in Mexico¿s National Population Program, the National Reproductive Health and Family Planning Program, and the Mexican program of the UN Population Fund. The lack of disaggregated information and of research, except for a handful of states with particularly grave demographic and reproductive health problems, were barriers to evaluation. It also appeared indispensable to analyze the situations of the nongovernmental organizations involved, and to define priorities among remaining tasks. Two achievements of the forum in Puebla were to reconstitute a coordinating body for follow-up of the Program of Action with a specific work plan, and to reinforce links and communication with state population councils and health institutions in order to facilitate implementation of the Program of Action. Among the 53 organizations represented at the Puebla Forum, 66% were involved in actions to fight poverty and 90% in actions to increase autonomy of women. 74% had ties to government agencies. The themes receiving most attention were sexuality and family planning, pregnancy and delivery, and HIV and other sexually transmitted diseases.

  6. Comment on the in-core measurement in the WWER nuclear power plant

    International Nuclear Information System (INIS)

    Krett, V.; Dach, K.; Erben, O.

    1985-01-01

    The activity of the Nuclear Research Institute (NRI) Rez in the field of in-core measurement sensors is described in the paper. The results of comparison and calibration experiments realized on the WWR-S research reactor at the NRI are presented. Measurements with fission calorimeters and SPN detectors carried out in the framework of diagnostic fuel assembly program of WWER NPP reactors are described. Noise measurements with detectors of in-core instrumentation of diagnostic fuel assemblies are also mentioned. Comparison experiments on the WWER-440 NPP reactor are described and the method of function verification of neutron sensors of the in-core control system of these reactors is given. (author)

  7. MANHATTAN PROJECT B REACTOR HANFORD WASHINGTON [HANFORD'S HISTORIC B REACTOR (12-PAGE BOOKLET)

    Energy Technology Data Exchange (ETDEWEB)

    GERBER MS

    2009-04-28

    The Hanford Site began as part of the United States Manhattan Project to research, test and build atomic weapons during World War II. The original 670-square mile Hanford Site, then known as the Hanford Engineer Works, was the last of three top-secret sites constructed in order to produce enriched uranium and plutonium for the world's first nuclear weapons. B Reactor, located about 45 miles northwest of Richland, Washington, is the world's first full-scale nuclear reactor. Not only was B Reactor a first-of-a-kind engineering structure, it was built and fully functional in just 11 months. Eventually, the shoreline of the Columbia River in southeastern Washington State held nine nuclear reactors at the height of Hanford's nuclear defense production during the Cold War era. The B Reactor was shut down in 1968. During the 1980's, the U.S. Department of Energy began removing B Reactor's support facilities. The reactor building, the river pumphouse and the reactor stack are the only facilities that remain. Today, the U.S. Department of Energy (DOE) Richland Operations Office offers escorted public access to B Reactor along a designated tour route. The National Park Service (NPS) is studying preservation and interpretation options for sites associated with the Manhattan Project. A draft is expected in summer 2009. A final report will recommend whether the B Reactor, along with other Manhattan Project facilities, should be preserved, and if so, what roles the DOE, the NPS and community partners will play in preservation and public education. In August 2008, the DOE announced plans to open B Reactor for additional public tours. Potential hazards still exist within the building. However, the approved tour route is safe for visitors and workers. DOE may open additional areas once it can assure public safety by mitigating hazards.

  8. Seasonality of major aerosol species and their transformations in Cairo mega-city

    International Nuclear Information System (INIS)

    Favez, O.; Cachier, H.; Sciare, J.; Alfaro, S.C.; El-Araby, T.M.; Harhash, M.A.; Abdelwahab, M.M.

    2008-01-01

    Bulk aerosols sampled oil a weekly basis at two Cairo (Egypt) urban sites from January 2003 to May 2006 were analysed for their chemical composition of major aerosol species (elemental carbon, water soluble/insoluble organic carbon, nitrate, sulphate, ammonium, chloride, sodium and calcium). Data subsequently obtained constitute one of the longest and more detailed dataset related to Cairo aerosols, and offer the opportunity to investigate seasonal trends. Dust aerosols (derived from calcium measurements) displayed maximum concentrations in spring and winter, due to frequent dust storms, but also high background concentration levels (∼ 50 μgm -3 ), all year long. Within these particles, about 40% oil average of Ca 2+ was found to be associated SO 4 2- , NO 3 - and/or Cl - , pointing out 'dust anthropization' processes and their subsequent climatic impact oil a regional scale. Seasonal variations of non-dust aerosols, equally distributed between carbonaceous aerosols and ions, were also observed, with concentrations of the order of 100 μgm -3 in autumn and winter, and of 60 μgm -3 in spring and summer. High concentration levels of non-sea-salt chloride (up to 15 μg m -3 on a monthly basis), likely of industrial origin, were observed in autumn and winter. During the autumn 'Black Cloud' event, biomass burning aerosols originating front rice straw burning in the Nile Delta have shown to account for 12%, 35%, and 50% of Cairo EC, WIOC and WSOC mass concentrations, respectively. Finally, relatively low WSOC/OC ratios (similar to 1/3) were obtained all the year long, calling for more investigation oil the water-solubility of organic aerosols originating from the burning of agricultural waste, and oil that of secondary organic aerosols formed in dry urban atmospheres. (authors)

  9. Implementation of U.S. Department of Energy physical protection upgrades in Lithuania and Uzbekistan

    International Nuclear Information System (INIS)

    Haase, M.; Romesberg, L.; Showalter, R.; Soo Hoo, M.S.; Corey, J.; Engling, E.

    1996-01-01

    Since 1994, the U.S. Department of Energy (DOE) has provided cooperative assistance to the non-nuclear weapons states of the Former Soviet Union. This effort, within DOE's program of Material Protection, Control, and Accounting (MPC ampersand A), identified the Institute of Nuclear Physics (INP) in Uzbekistan and the Ignalina Nuclear Power Plant (INPP) in Lithuania as sites for cooperative MPC ampersand A projects. The INP, located just outside of Tashkent, is the site of a 10-megawatt WWR-SM research reactor. This reactor is expected to remain operational as a major nuclear research and isotope production reactor for Central Asia. The INPP, located 100 kilometers northeast of the capital city of Vilnius, consists of two Russian-made RBMK reactors with a combined power output of 3,000 megawatts (electric). This power plant has been the subject of international safety and security concerns, which prompted DOE's cooperative assistance effort. This paper describes U.S. progress in a multi-national effort directed at implementing physical protection upgrades in Lithuania and Uzbekistan. The upgrades agreed upon between DOE and the INP and between DOE and the INPP have been designed to interface with upgrades being implemented by other donor countries. DOE/INPP upgrade projects include providing training on U.S. approaches to physical protection, access control through the main vehicle portal, a hardened central alarm station, and improved guard force communications. DOE/INP upgrade projects in Uzbekistan include an access control system, a hardened fresh fuel storage vault, an interior intrusion detection and assessment system, and an integrated alarm display and assessment system

  10. Reactor neutron activation analysis on reference materials from intercomparison runs

    International Nuclear Information System (INIS)

    Pantelica, A.; Salagean, M.

    2003-01-01

    A review of using the Instrumental Neutron Activation Analysis (INAA) technique in our laboratory to determine major, minor and trace elements in mineral and biological samples from international intercomparison runs organised by IAEA Vienna, IAEA-MEL Monaco, 'pb-anal' Kosice, INCT Warszawa and IPNT Krakow is presented. Neutron irradiation was carried out at WWR-S reactor in Bucharest (short and long irradiation) during 1982-1997 and at TRIGA reactor in Pitesti (long irradiation) during the later period. The following type of materials were analysed: soils, marine sediments, uranium phosphate ore, water sludge, copper flue dust, whey powder, yeast, cereal flour (rye and wheat), marine animal tissue (mussel, garfish and tuna fish), as well as vegetal tissue (seaweed, cabbage, spinach, alfalfa, algae, tea leaves and herbs). The following elements could be, in general, determined: Ag, As, Au, Ba, Br, Ca, Ce, Co, Cr, Cs, Eu, Fe, Hf, Hg, K, La, Lu, Mo, Na, Nd, Ni, Rb, Sb, Sc, Se, Sm, Sr, Ta, Tb, Th, U, W, Yb and Zn of long-lived radionuclides, as well as Al, Ca, Cl, Cu, Mg, Mn, and Ti of short-lived radionuclides. Data obtained in our laboratory for various matrix samples presented and compared with the intercomparison certified values. The intercomparison exercises offer to the participating laboratories the opportunity to test the accuracy of their analytical methods as well as to acquire valuable Reference Materials/ standards for future analytical applications. (authors)

  11. U.S. Nuclear Power Reactor Plant Status

    Data.gov (United States)

    Nuclear Regulatory Commission — Demographic data on U.S. commercial nuclear power reactors, including: plant name/unit number, docket number, location, licensee, reactor/containment type, nuclear...

  12. Analytical Characterization of Rococo Paintings in Egypt: Preliminary Results from El-Gawhara Palace at Cairo

    Directory of Open Access Journals (Sweden)

    Fatma REFAAT

    2012-12-01

    Full Text Available El-Gawhara palace (1813–1814 AD is situated south of the Mosque of Muhammad Ali in the Cairo Citadel. This palace is an important example of the best early 19th century rococo decorations in Egypt. The present study reports some of the results obtained from the application of different analytical techniques to characterize some rococo paintings at El-Gawhara palace at Cairo, Egypt. The characterization of the studied paintings was carried out by means of optical microscopy (OM, scanning electron microscopy equipped with an energy dispersive X-ray detector (EDS and Fourier transform infrared spectroscopy (FT−IR. The obtained results allowed the identification of the chemical composition, structure and the painting technique employed in these paintings. This methodology reveals some useful information on some rococo paintings dating back to the 19th century in Egypt.

  13. Advances in U.S. reactor physics standards

    International Nuclear Information System (INIS)

    Cokinos, Dimitrios

    2008-01-01

    The standards for Reactor Design, widely used in the nuclear industry, provide guidance and criteria for performing and validating a wide range of nuclear reactor calculations and measurements. Advances, over the past decades in reactor technology, nuclear data and infrastructure in the data handling field, led to major improvements in the development and application of reactor physics standards. A wide variety of reactor physics methods and techniques are being used by reactor physicists for the design and analysis of modern reactors. ANSI (American National Standards Institute) reactor physics standards, covering such areas as nuclear data, reactor design, startup testing, decay heat and fast neutron fluence in the pressure vessel, are summarized and discussed. These standards are regularly undergoing review to respond to an evolving nuclear technology and are being successfully used in the U.S and abroad contributing to improvements in reactor design, safe operation and quality assurance. An overview of the overall program of reactor physics standards is presented. New standards currently under development are also discussed. (authors)

  14. Neutron radiography

    International Nuclear Information System (INIS)

    Hrdlicka, Z.

    1977-01-01

    Neutron radiography is a radiographic method using a neutron beam of a defined geometry. The neutron source usually consists of a research reactor, a specialized neutron radiography reactor or the 252 Cf radioisotope source. There are two types of the neutron radiography display system, viz., a system producing neutron radiography images by a photographic process or a system allowing a visual display, eg., using a television monitor. The method can be used wherever X-ray radiography is used except applications in the radiography of humans. The neutron radiography unit at UJV uses the WWR-S reactor as the neutron source and both types of the above mentioned display system. (J.P.)

  15. ELISA-seroprevalence of Toxoplasma gondii in draught horses in Greater Cairo, Egypt.

    Science.gov (United States)

    Haridy, Fouad M; Shoukry, Nahla M; Hassan, Aly Awad; Morsy, Tosson A

    2009-12-01

    Toxoplasma gondii is one of the important zoonotic parasites of worldwide. In this paper the seroprevalence of T. gondii in draught horses (3-15 years) including 90 males and 10 females in the first half of the year 2009 was studied. The result showed that the overall ELISA-T. gondii antibodies were 25% of the horses in Greater Cairo, 50% (females) and 22.2% (males).

  16. Difficult airway management patterns among anesthesiologists practicing in Cairo University Hospitals

    Directory of Open Access Journals (Sweden)

    Neamat I. Abdel rahman

    2016-01-01

    Conclusion: The practice of anesthesiologists in Cairo university hospitals is close to the recommendations of the ASA guidelines for management of difficult airway. There is increased skills in fiberoptic bronchoscopes and SGA with increased frequency of difficult airway managements training courses; however, they need to improve their skills in awake fiberoptic intubations technique and they need to be trained on invasive airway management access to close the discrepancy between their theoretical choices in different situations and their actual skills.

  17. Evaluation of neutron flux in the WWR-SM reactor channel and in the irradiating zone of U-150 cyclotron

    International Nuclear Information System (INIS)

    Sadikov, I.I.; Zinov'ev, V.G.; Sadikova, Z.O.; Salimov, M.I.

    2006-01-01

    Full text: For effective work of a reactor, and correct planning of experiments related to the reactor irradiation of various materials it is required to control a neutron flux in the given irradiation point for a long irradiation period. For realization of research works on topazes ennobling under irradiation by reactor neutrons as well as by secondary neutrons produced in a cyclotron it is necessary to know the total neutron flux and spectra. To resolve the problem a technique for registration of neutrons with different energy and calculation of a neutrons spectrum in the given irradiation points in reactor channels and in cyclotron behind the nickel target has been developed. Neutron flux density and energy spectra were monitored by use of the following nuclear reactions: 59 Co(n,γ) 60 Co, 197 Au(n,γ) 198 Au, 58 Ni(n,p) 58 Co, 24 Mg(n,p) 24 Na, 48 Ti(n,p) 48 Sc, 46 Ti(n,p) 46 Sc, 54 Fe(n,p) 54 Mn, 89 Y(n,2n) 88 Y, 60 Ni(np) 60 Co. Gamma spectrometer composed of HPGe detector (Rel. Eff. - 15%) and Digital Spectra Analyzer DSA-1000 (Canberra Ind., USA) was used to measure gamma activity of irradiated samples. Acquired gamma spectra were processed by means of Genie 2000 standard software package. The σ(E) functions and neutron spectra were calculated by using the least squares method and approximating the tabular and experimental data with power polynomials. The developed technique was applied for the adjustment of the topazes irradiation regimes in the reactor core and under secondary neutrons flux from a nickel target in the cyclotron. The given technique allows to calculate a logarithmic spectrum of neutrons in a energy range from 0,025 eV up to 12 MeV with the uncertainty of about 10 %. (author)

  18. Identification of Chemical Reactor Plant’s Mathematical Model

    OpenAIRE

    Pyakullya, Boris Ivanovich; Kladiev, Sergey Nikolaevich

    2015-01-01

    This work presents a solution of the identification problem of chemical reactor plant’s mathematical model. The main goal is to obtain a mathematical description of a chemical reactor plant from experimental data, which based on plant’s time response measurements. This data consists sequence of measurements for water jacket temperature and information about control input signal, which is used to govern plant’s behavior.

  19. Reduction of lead pollution from vehicular emissions in cairo Part 1: Comparison of alternative solutions

    International Nuclear Information System (INIS)

    El-Haggar, S.M.; Saleh, S.K.; El-Kady, M.A.

    1996-01-01

    It has been recognized for decades that the major source of lead pollution is lead additives to automotive fuels. This problem has been countered in most countries in europe and Usa by introducing alternative anti-knock chemicals and unleaded gasoline. In egypt lead is still being added to gasoline in large quantities. However, progress has been made, and unleaded gasoline is currently being produced in Alexandria. Nevertheless, the major pollution problem remains in the Greater Cairo region as indicated by the atmospheric lead levels and the lead blood levels of the children in Cairo. The aim of the present study is to find an optimum solution to this problem. A comparison of the different solutions is conducted in order to come up with the most feasible solution to this urgent problem. In conclusion it has been demonstrated that the elimination of lead additives, with its huge positives effects on the country environment, proved to be profitable. 4 figs., 2 tabs

  20. Identification of Chemical Reactor Plant’s Mathematical Model

    Directory of Open Access Journals (Sweden)

    Pyakillya Boris

    2015-01-01

    Full Text Available This work presents a solution of the identification problem of chemical reactor plant’s mathematical model. The main goal is to obtain a mathematical description of a chemical reactor plant from experimental data, which based on plant’s time response measurements. This data consists sequence of measurements for water jacket temperature and information about control input signal, which is used to govern plant’s behavior.

  1. Operating history of U.S. nuclear power reactors

    International Nuclear Information System (INIS)

    1974-01-01

    The operating history of U. S. nuclear power plants through December 31, 1974 has been collected. Included are those nuclear reactor facilities which produce electricity, even if in token amounts, or which are part of a development program concerned with the generation of electricity through the use of a nuclear reactor as a heat source. The information is based on data furnished by facility operators. The charts are plotted in terms of cumulative thermal energy as a function of time. Since only those shutdowns of five days or more are shown, the charts do not give a detailed history of plant operation. They do, however, give an overview of the operating history of a variety of developmental and experimental nuclear power reactors. The data show the yearly gross generation of electricity for each U. S. nuclear plant and, for civilian power plants, information on reactor availability and plant capacity factor. (U.S.)

  2. Research about reactor operator's personability characteristics and performance

    Energy Technology Data Exchange (ETDEWEB)

    Wei Li; He Xuhong; Zhao Bingquan [Tsinghua Univ., Institute of Nuclear Energy Technology, Beijing (China)

    2003-03-01

    To predict and evaluate the reactor operator's performance by personality characteristics is an important part of reactor operator safety assessment. Using related psychological theory combined with the Chinese operator's fact and considering the effect of environmental factors to personality analysis, paper does the research about the about the relationships between reactor operator's performance and personality characteristics, and offers the reference for operator's selection, using and performance in the future. (author)

  3. Crime in relation to urban design. Case study: The Greater Cairo Region

    Directory of Open Access Journals (Sweden)

    Heba Adel

    2016-09-01

    Full Text Available Crime is a part of any social system and known to human communities since its origins. It differs from community to another, even within one community it doesn’t occur equally in all places and nor by the same way. It is also concentrated in some places more than others, sometimes increases, sometimes decreases, etc. Previous researches have proved that crime rate has significant correlation with different social factors: education levels, poverty rates and lack of social organization, while others have drawn the attention to its relation with the built environment. They proposed that crime occurs in places where both opportunities and criminals are available. The role of this paper is to identify urban circumstances related to crime occurrence within the Greater Cairo Region, and to propose different ways to reduce these crimes. Consecutively, agglomeration’s main districts were scrutinized according to social analysis, street-network pattern and land-use.

  4. History of fast reactor development in U.S.A.-I

    International Nuclear Information System (INIS)

    Ninokata, Hisashi; Sasao, Nobuyki

    2007-01-01

    History and present state of fast reactor was reviewed in series. As a history of fast reactor development in U.S.A. - I, this third lecture presented the dawn of the fast reactor development in the USA. The first fast reactor was the Clementine reactor with plutonium fuels and mercury coolant. The LAMPRE-1 reactor was the first sodium cooled and molten plutonium reactor. Experimental breeder reactor (EBR-1) was the first reactor to produce electricity and four kinds of fuels were loaded. Zero-power reactors were constructed to conduct reactor physics experiments on fast reactors. Today there are renewed interests in fast reactors due to their ability to fission actinides and reduce radioactive wastes. (T. Tanaka)

  5. Ecological Risk Assessment of Metal Pollution along Greater Cairo Sector of the River Nile, Egypt, Using Nile Tilapia, Oreochromis niloticus, as Bioindicator

    Directory of Open Access Journals (Sweden)

    Wael A. Omar

    2015-01-01

    Full Text Available The present work aims to evaluate seasonal metal pollution along Greater Cairo sector of the River Nile, Egypt, using wild Nile tilapia, Oreochromis niloticus, as bioindicator and to conduct a risk assessment for human consumers. Greater Cairo is the largest populated area along the whole course of River Nile with a wide range of anthropogenic activities. Effects of metal pollution on fish body indices were studied using condition factor (CF and scaled mass index (SMI. Metal pollution index (MPI showed that the total metal load in fish organs followed the follwoing order: kidney > liver > gill > muscle which gives a better idea about the target organs for metal accumulation. Metal concentrations in fish muscle (edible tissue showed the following arrangement: Fe > Zn > Cu > Mn > Pb > Cd. Metal’s bioaccumulation factor (BAF in fish muscle showed the following arrangement: Zn > Cu > Fe > Mn > Cd and Pb. The hazard index (HI as an indicator of human health risks associated with fish consumption showed that adverse health effects are not expected to occur in most cases. However, the metals’ cumulative risk effects gave an alarming sign specifically at high fish consumption rates.

  6. Agreement for the Establishment in Cairo of a Middle Eastern Regional Radioisotope Centre for the Arab Countries

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1962-10-18

    On 14 September 1962 the Board of Governors approved an Agreement for the establishment in Cairo of a Middle Eastern regional radioisotope centre for the Arab countries. The text of this Agreement is reproduced in this document for the information of all Members.

  7. Agreement for the Establishment in Cairo of a Middle Eastern Regional Radioisotope Centre for the Arab Countries

    International Nuclear Information System (INIS)

    1962-01-01

    On 14 September 1962 the Board of Governors approved an Agreement for the establishment in Cairo of a Middle Eastern regional radioisotope centre for the Arab countries. The text of this Agreement is reproduced in this document for the information of all Members

  8. Cairo youth declaration.

    Science.gov (United States)

    Ladjali, M

    1995-01-01

    More than 100 young people from 56 countries voiced their needs and concerns in a Youth Consultation held just before the International Conference on Population and Development (ICPD), August 31 to September 4, 1994. Many journalists from the international press followed the consultation and interviewed the youths, with a short film even produced on the proceedings. After discussing the main topics of the ICPD, participants produced a Youth Declaration with recommendations for action and conclusions for partnership. More than 20 participants remained in Cairo to present consultation conclusions in well-attended workshops and role play at the ICPD NGO Forum. One representative presented the Youth Declaration in ICPD plenary session. These young men and women from all regions of the world, from a diversity of cultural, religious, and political backgrounds found common ground on the need for population concerns to be explicitly and consistently integrated with development in the context of a just and equitable international economic system; a strong focus upon youth education and mobilization in the areas of adolescent health, sexual and reproductive health, the environment, human rights, and political and economic systems; and the sense that now is the time to act at the individual, organizational, national, and national levels. Education and safe sexual behavior do not encourage promiscuity. On the contrary, they promote and enhance healthy, responsible relationships, minimizing the incidence of unplanned pregnancies and sexually transmitted infections when sex does take place. Participants recommend promoting peer education; involving and educating peers through artistic activities such as music and drama; implementing peer counseling and raising awareness through one-on-one interaction, group discussions, printed media, and radio programs; organizing services for youths in a variety of settings; creating jobs for youths in cooperatives and businesses; educating

  9. NILES 94; International Conference Held in Cairo, Egypt on 26-30 March 1994

    Science.gov (United States)

    1994-03-30

    Conference, March 26-30, 1994 IL-M-12, Mon. 28,9:30 The Use of Laser in Oesophagogastric Carcinoma in the Gastrointestinal Endoscopy Unit, Cairo University...University. of dysphagia waqs obtained in all cases. Initial responce was relatd to the site and growth pattern of the tumour. Reobliteratoin rate was...gall stones. Endoscopy 18:95-96, 1986. 3. Nishioka NS et al., : Mechanism of laser induced framentation of urinary and biliary calculi laser life Sci

  10. The U.S. Geological Survey's TRIGA® reactor

    Science.gov (United States)

    DeBey, Timothy M.; Roy, Brycen R.; Brady, Sally R.

    2012-01-01

    The U.S. Geological Survey (USGS) operates a low-enriched uranium-fueled, pool-type reactor located at the Federal Center in Denver, Colorado. The mission of the Geological Survey TRIGA® Reactor (GSTR) is to support USGS science by providing information on geologic, plant, and animal specimens to advance methods and techniques unique to nuclear reactors. The reactor facility is supported by programs across the USGS and is organizationally under the Associate Director for Energy and Minerals, and Environmental Health. The GSTR is the only facility in the United States capable of performing automated delayed neutron analyses for detecting fissile and fissionable isotopes. Samples from around the world are submitted to the USGS for analysis using the reactor facility. Qualitative and quantitative elemental analyses, spatial elemental analyses, and geochronology are performed. Few research reactor facilities in the United States are equipped to handle the large number of samples processed at the GSTR. Historically, more than 450,000 sample irradiations have been performed at the USGS facility. Providing impartial scientific information to resource managers, planners, and other interested parties throughout the world is an integral part of the research effort of the USGS.

  11. Magnetic structure of post-perovskite compound CaIrO3

    International Nuclear Information System (INIS)

    Ohgushi, Kenya; Ohsumi, Hiroyuki; Yamaura, Jun-ichi; Arima, Taka-hisa

    2014-01-01

    We have performed resonant X-ray diffraction experiments at the Ir L absorption edges for a post-perovskite compound CaIrO 3 with a Ir 4+ : (t 2g ) 5 electronic configuration. By observing the magnetic signals, we could clearly see that the magnetic structure was a striped ordering with antiferromagnetic moments along the c axis and that the wave function of a t 2g hole is strongly spin-orbit entangled, the J eff = 1/2 state. The observed spin arrangement is consistent with a theoretical work predicting a unique superexchange interaction called the quantum compass model. Our studies stimulate further studies for developing novel quantum states in iridium oxides. (author)

  12. Indian Academy of Sciences. Volume 105. Number 6. December 1993. Proceedings of the International Conference on Solar Energy Storage Applied Photochemistry (2nd) Held in Cairo, Egypt on 6-11 January 1993

    Science.gov (United States)

    1993-12-01

    C.hemic. Onivermuiti~ (ll Dfuisburg. l).470411 Duiisburg, (eicrim.%s ’Present address- Department of Chemiiitry. C"airo University, Giza . Cairo, Egypt... pyramid or in a "capped icosahedron". The double pyramid has flat sides and a flat surface and reacts very poorly with hydrogen molecules. The capped

  13. Prospects of closed-circuit television in detecting surface defects

    International Nuclear Information System (INIS)

    Kaisler, L. et al.

    The use is discussed of closed-circuit television for optical in-service testing of surface defects of nuclear reactors. Experience gained by UJV Rez with in-service testing of the WWR-S reactor is briefly reported. Main attention is devoted to recognizability of defects and to determining the fundamental conditions of the applicability and limitations of the closed-circuit television method. In experiments, resolution of the method was tested and the role of the human factor was assessed in evaluating the results. The need was stressed of thorough training of operators. Based on the experiments conducted, considerations are presented regarding modifications of the individual elements of the tv chain aimed at improved quality of information and a limited role of the observer. (B.S.)

  14. Attitudes of Cairo University medical students toward smoking: the need for tobacco control programs in medical education.

    Science.gov (United States)

    Khan, Adeel A M; Dey, Subhojit; Taha, Alaa H; Huq, Farhan S; Moussawi, Ahmad H; Omar, Omar S; Soliman, Amr S

    2012-04-01

    Tobacco smoking rates are increasing in developing countries and so are tobacco-related chronic diseases. Reported figures from the WHO show rates of smoking in Egypt as high as 20% but limited information is available about smoking specifically among physicians and medical students. Final-year medical students of Cairo University were surveyed regarding their tobacco behavior and attitudes using a modified Global Health Professions Student Survey. We approached 220 students by randomly selecting clinical units into which they were assigned and requested completion of the survey. Ever users of some form of tobacco comprised 46.7% of students sampled, current users of cigarettes comprised 17.4%, and current users of water pipe 'sheesha' comprised 17.6%. The vast majority (87.7%) of students believed that smoking is a public health problem in Cairo and supported restriction of tobacco. Yet, only 58.5% stated that they were taught it is important for physicians to provide tobacco education materials to patients. Among ever users of cigarettes, 54.4% believed health professionals do not serve as health role models for patients, and only a small percentage of all students (34.2%) stated that they had received some form of training on smoking cessation in their medical curriculum to be able to instruct patients. A high rate of smoking was revealed among medical students in Cairo. Overall, approximately 23.4% of students were currently smoking cigarettes and/or sheesha, and 46.7% were ever users of some form of tobacco. A formal antitobacco program for medical students should be incorporated into their medical curriculum to change the attitudes of medical students and overcome the anticipated increase in chronic diseases in Egypt.

  15. Provenance studies of pottery fragments from medieval Cairo, Egypt

    International Nuclear Information System (INIS)

    Beal, J.W.; Olmez, I.

    1997-01-01

    In the analysis of archeological pottery fragments, instrumental neutron activation analysis has been utilized to establish the elemental concentrations of up to 37 chemical elements for each of 53 archeological pottery samples from medieval Cairo, Egypt, and one additional sample of Chinese porcelain. These elemental concentrations have been utilized in a statistical analysis procedure in order to determine similarities and correlations between the various samples. Multivariate analyses have been used to quantitatively determine these interrelationships. This methodology successfully separated the Egyptian samples into two broad categories: polychrome decorated ceramic ware and monochrome celadon ware. In addition the methodology successfully identified the one unique sample of Chinese porcelain. Several samples appeared to be either a mixture of categories or outliers in the data set and were not attributable to any distinct category. (author)

  16. Environmental pollution study around a large industrial area near Cairo, Egypt

    International Nuclear Information System (INIS)

    Abdel-Halim, A.S.

    2003-01-01

    Neutron activation analysis is one of the most extensively used methods for environmental studies due to its high sensitivity, precision, versatility and multielemental character. Cement factories at Helwan, south of Cairo, contribute substantially to environmental pollution. Determination of minor and trace-elements in dust particulates from the cement industrial areas has been performed to assess the air quality from an environmental and human health point of view. Soil-7 standard reference material from IAEA and SRM-1571 from NBS were used for quality assurance testing. The data obtained indicate there is an indication that the pollution could be hazardous to people living in and around the area surveyed. (author)

  17. Ways of prevention of accidents at atomic reactor

    International Nuclear Information System (INIS)

    Takibaev, Zh. S.

    2000-01-01

    The methods proposed to prevent such a move are discussed as well as the scheme of their realization. To improve reactor operation characteristics the safeguard system of quick response is used. Nowadays direct-acting safeguard system (DAS) is to be worked out. It reacts on the main cause of the accident the rapid growth of neutron flux. The time delay of combined gas-liquid DAS unit and fluctuation of nuclear power are calculated. The DAS grid disposed in active zone is developed. Fissile materials are employed because their heating almost immediately follows the growth of neutron flux. There are several systems proposed: uranium bimetal dispersed absorber, uranium hexafluoride liquid absorber (gadolinium solution).Neutronic calculation is done for WWR-1000. The model suggested acts over 0.12 sec. after reactivity swing of 0.003, becomes a 'safety rod' over time delay of 1.49 sec. and cleans itself over 3.0 sec. after.The study presents its improved version. Absorber is injected dose by dose and thus negative reactivity is introduced discretely. Accordingly the same system can act by extracting some parts of fuel from the core. Bimetal safeguard systems are studied. The methods suggested above seem proved in the sense of strengthening nuclear energy development in the future. The problem of DAS and other safeguard systems to prevent reactivity accidents for various reactor types including computer simulation is set to be studied further

  18. New cities between sustainability and real estate investment: A case study of New Cairo city

    Directory of Open Access Journals (Sweden)

    Reham M. Hafez

    2017-04-01

    This research reviews the basis of development of the new cities. The influence of the real estate investment in some Arab countries, then it handles the case study – “New Cairo city”. Discussing all the investing factors made the city in its current status. Then comes the recommendations in a trial to get an alternative structure to achieve sustainability in light of the current determinants and growth stages.

  19. On Selection of the Probability Distribution for Representing the Maximum Annual Wind Speed in East Cairo, Egypt

    International Nuclear Information System (INIS)

    El-Shanshoury, Gh. I.; El-Hemamy, S.T.

    2013-01-01

    The main objective of this paper is to identify an appropriate probability model and best plotting position formula which represent the maximum annual wind speed in east Cairo. This model can be used to estimate the extreme wind speed and return period at a particular site as well as to determine the radioactive release distribution in case of accident occurrence at a nuclear power plant. Wind speed probabilities can be estimated by using probability distributions. An accurate determination of probability distribution for maximum wind speed data is very important in expecting the extreme value . The probability plots of the maximum annual wind speed (MAWS) in east Cairo are fitted to six major statistical distributions namely: Gumbel, Weibull, Normal, Log-Normal, Logistic and Log- Logistic distribution, while eight plotting positions of Hosking and Wallis, Hazen, Gringorten, Cunnane, Blom, Filliben, Benard and Weibull are used for determining exceedance of their probabilities. A proper probability distribution for representing the MAWS is selected by the statistical test criteria in frequency analysis. Therefore, the best plotting position formula which can be used to select appropriate probability model representing the MAWS data must be determined. The statistical test criteria which represented in: the probability plot correlation coefficient (PPCC), the root mean square error (RMSE), the relative root mean square error (RRMSE) and the maximum absolute error (MAE) are used to select the appropriate probability position and distribution. The data obtained show that the maximum annual wind speed in east Cairo vary from 44.3 Km/h to 96.1 Km/h within duration of 39 years . Weibull plotting position combined with Normal distribution gave the highest fit, most reliable, accurate predictions and determination of the wind speed in the study area having the highest value of PPCC and lowest values of RMSE, RRMSE and MAE

  20. VIRTUAL PLATFORMS FOR HERITAGE PRESERVATION IN THE MIDDLE EAST: THE CASE OF MEDIEVAL CAIRO

    Directory of Open Access Journals (Sweden)

    Mohamed Gamal Abdelmonem

    2017-11-01

    Full Text Available Much of the effort in VH is directed towards accurate representation of historic structures, objects or artefacts. There is little attention is paid, however, to the human aspects of city life, the intangible heritage to which people can actually relate. Digital models of historic buildings and spaces only give a sense of precision. Yet, rituals, human attitude and cultural traditions remained a gap in current research and advanced technology in heritage visualization. Virtual Heritage Environments (VHE suffer from the lack of ‘thematic interactivity’ due to the limited cultural content and engaging modules largely used in photorealistic video gaming systems. In order to approach virtual fidelity and accurate reproduction of historic environments, this paper reports on a research process to investigate and incorporate a Cultural-feed into digital platforms of Virtual Heritage. In doing so, the paper focuses on the Middle East in general and Medieval Cairo in particular. It discusses conceptual and practical framework for the development of virtual heritage platforms as a research, educational and engagement tool that brings historic spaces and buildings back to the recognition of the public eye of the ordinary user. It analyses current practices and projects of the virtual heritage technologies and reports on field work that took place in Islamic Cairo with Five Start-Up entrepreneurs.

  1. Fuel Management at the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Pham, V.L.; Nguyen, N.D.; Luong, B.V.; Le, V.V.; Huynh, T.N.; Nguyen, K.C. [Nuclear Research Institute, 01 Nguyen Tu Luc Street, Dalat City (Viet Nam)

    2011-07-01

    The Dalat Nuclear Research Reactor (DNRR) is a pool type research reactor which was reconstructed in 1982 from the old 250 kW TRIGA-MARK II reactor. The spent fuel storage was newly designed and installed in the place of the old thermalizing column for biological irradiation. The core was loaded by Russian WWR-M2 fuel assemblies (FAs) with 36% enrichment. The reconstructed reactor reached its initial criticality in November 1983 and attained it nominal power of 500 kW in February 1984. The first fuel reloading was executed in April 1994 after more than 10 years of operation with 89 highly enriched uranium (HEU) FAs. The third fuel reloading by shuffling of HEU FAs was executed in June 2004. After the shuffling the working configuration of reactor core kept unchanged of 104 HEU FAs. The fourth fuel reloading was executed in November 2006. The 2 new HEU FAs were loaded in the core periphery, at previous locations of wet irradiation channel and dry irradiation channel. After reloading the working configuration of reactor core consisted of 106 HEU FAs. Contracts for reactor core conversion between USA, Russia, Vietnam and the International Atomic Energy Agency for Nuclear fuel manufacture and supply for DNRR and Return of Russian-origin non-irradiated highly enriched uranium fuel to the Russian Federation have been realized in 2007. According to the results of design and safety analyses performed by the joint study between RERTR Program at Argonne National Laboratory and Vietnam Atomic Energy Institute the mixed core configurations of irradiated HEU and new low enriched uranium (LEU) FAs has been created on 12 September, 2007 and on 20 July, 2009. After reloading in 2009, the 14 HEU FAs with highest burnup were removed from the core and put in the interim storage in reactor pool. The works on full core conversion for the DNRR are being realized in cooperation with the organizations, DOE and IAEA. Contract for Nuclear fuel manufacture and supply of 66 LEU FAs for DNRR

  2. Metropolitan food supply : case study Cairo : a quick scan study to enhance fresh food supply and minimize postharvest losses

    NARCIS (Netherlands)

    Broek, van den W.H.A.M.; Boerrigter, H.A.M.

    2014-01-01

    To investigate options for “Metropolitan food production systems” in Egypt and specifically in the Cairo region, a ‘cold chain quick scan’ is conducted by Wageningen UR post-harvest specialists. The study comprehends a quick scan for market demand, market willingness and a search for trend

  3. Risk perception and priority setting for intervention among hepatitis C virus and environmental risks: a cross-sectional survey in the Cairo community

    Directory of Open Access Journals (Sweden)

    Dewedar Sahar

    2010-12-01

    Full Text Available Abstract Background Hepatitis C virus (HCV recently emerged as a major public health hazard in Egypt. However, dramatic healthcare budget constraints limit access to the costly treatment. We assessed risk perception and priority setting for intervention among HCV, unsafe water, and outdoor air pollution in Cairo city. Methods A survey was conducted in the homes of a representative sample of household heads in Cairo city. Risk perception was assessed using the "psychometric paradigm" where health hazards are evaluated according to several attributes and then summarized by principal component analysis. Priority setting was assessed by individual ranking of interventions reducing health hazards by 50% over five years. The Condorcet method was used to aggregate individual rankings of the three interventions (main study or two of three interventions (validation study. Explanatory factors of priority setting were explored in multivariate generalized logistic models. Results HCV was perceived as having the most severe consequences in terms of illness and out-of-pocket costs, while outdoor air pollution was perceived as the most uncontrollable risk. In the main study (n = 2,603, improved water supply received higher priority than both improved outdoor air quality (60.1%, P P Conclusions The Cairo community prefers to further improving water supply as compared to improved outdoor air quality and screening and treatment of chronic hepatitis C.

  4. An Account of Oak Ridge National Laboratory's Thirteen Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, Murray Wilford [ORNL

    2009-08-01

    The Oak Ridge National Laboratory has built and operated 13 nuclear reactors in its 66-year history. The first was the graphite reactor, the world's first operational nuclear reactor, which served as a plutonium production pilot plant during World War II. It was followed by two aqueous-homogeneous reactors and two red-hot molten-salt reactors that were parts of power-reactor development programs and by eight others designed for research and radioisotope production. One of the eight was an all-metal fast burst reactor used for health physics studies. All of the others were light-water cooled and moderated, including the famous swimming-pool reactor that was copied dozens of times around the world. Two of the reactors were hoisted 200 feet into the air to study the shielding needs of proposed nuclear-powered aircraft. The final reactor, and the only one still operating today, is the High Flux Isotope Reactor (HFIR) that was built particularly for the production of californium and other heavy elements. With the world's highest flux and recent upgrades that include the addition of a cold neutron source, the 44-year-old HFIR continues to be a valuable tool for research and isotope production, attracting some 500 scientific visitors and guests to Oak Ridge each year. This report describes all of the reactors and their histories.

  5. Geological heritage under strong urbanization pressure: El-Mokattam and Abu Roash as examples from Cairo, Egypt

    Science.gov (United States)

    AbdelMaksoud, Kholoud M.; Al-Metwaly, Wael M.; Ruban, Dmitry A.; Yashalova, Natalia N.

    2018-05-01

    Urban geological heritage is prone to anthropogenic pressure linked to urbanization. In order to understand the necessity of conservation of such a heritage located in two areas of Cairo (Egypt), namely El-Mokattam and Abu Roash, their assessment is undertaken. It is established that the both areas possess geological heritage. As much as five types of the latter are represented in each of them. The most important in El-Mokattam is geomorphological type (the Mokattam Mountain itself), and the most important in Abu Roash are palaeogeographical (facies and palaeoecosystems) and structural (outcrop-scale fold and faults) types. In the both areas, the geological heritage is destroyed because of rapid and often uncontrolled (even illegal) urbanization. According to the results of the satellite images interpretation, the urban area has grown by 1.4 times in El-Mokattam and 3.4 times in Abu Roash during the period of 2000-2017 when many unique objects were damaged and destroyed. Some aesthetic properties have been also lost, which has decreased the important of these objects to tourists, as well as many students and researchers. Assigning official protected status and possible geopark creation can facilitate efficient conservation of the urban geological heritage of Cairo.

  6. Evaluation of The Surface Ozone Concentrations In Greater Cairo Area With Emphasis On Helwan, Egypt

    International Nuclear Information System (INIS)

    Ramadan, A.; Kandil, A.T.; Abd Elmaged, S.M.; Mubarak, I.

    2011-01-01

    Various biogenic and anthropogenic sources emit huge quantities of surface ozone. The main purpose of this study is to evaluate the surface ozone levels present at Helwan area in order to improve the knowledge and understanding troposphere processes. Surface Ozone has been measured at 2 sites at Helwan; these sites cover the most populated area in Helwan. Ozone concentration is continuously monitored by UV absorption photometry using the equipment O 3 41 M UV Photometric Ozone Analyzer. The daily maximum values of the ozone concentration in the greater Cairo area have approached but did not exceeded the critical levels during the year 2008. Higher ozone concentrations at Helwan are mainly due to the transport of ozone from regions further to the north of greater Cairo and to a lesser extent of ozone locally generated by photochemical smog process. The summer season has the largest diurnal variation, with the tendency of the daily ozone maxima occur in the late afternoon. The night time concentration of ozone was significantly higher at Helwan because there are no fast acting sinks, destroying ozone since the average night time concentration of ozone is maintained at 40 ppb at the site. No correlation between the diurnal total suspended particulate (TSP) matter and the diurnal cumulative ozone concentration was observed during the Khamasin period

  7. Risk perception and priority setting for intervention among hepatitis C virus and environmental risks: a cross-sectional survey in the Cairo community.

    Science.gov (United States)

    Schwarzinger, Michaël; Mohamed, Mostafa K; Gad, Rita R; Dewedar, Sahar; Fontanet, Arnaud; Carrat, Fabrice; Luchini, Stéphane

    2010-12-20

    Hepatitis C virus (HCV) recently emerged as a major public health hazard in Egypt. However, dramatic healthcare budget constraints limit access to the costly treatment. We assessed risk perception and priority setting for intervention among HCV, unsafe water, and outdoor air pollution in Cairo city. A survey was conducted in the homes of a representative sample of household heads in Cairo city. Risk perception was assessed using the "psychometric paradigm" where health hazards are evaluated according to several attributes and then summarized by principal component analysis. Priority setting was assessed by individual ranking of interventions reducing health hazards by 50% over five years. The Condorcet method was used to aggregate individual rankings of the three interventions (main study) or two of three interventions (validation study). Explanatory factors of priority setting were explored in multivariate generalized logistic models. HCV was perceived as having the most severe consequences in terms of illness and out-of-pocket costs, while outdoor air pollution was perceived as the most uncontrollable risk. In the main study (n = 2,603), improved water supply received higher priority than both improved outdoor air quality (60.1%, P report of HCV-related diseases in the household, and perception of HCV as the most severe risk were significantly associated to setting HCV treatment as the first priority. The Cairo community prefers to further improving water supply as compared to improved outdoor air quality and screening and treatment of chronic hepatitis C.

  8. Assessment methodology applicable to safe decommissioning of Romanian VVR-S research reactor

    International Nuclear Information System (INIS)

    Baniu, O.; Vladescu, G.; Vidican, D.; Penescu, M.

    2002-01-01

    The paper contains the results of research activity performed by CITON specialists regarding the assessment methodology intended to be applied to safe decommissioning of the research reactors, developed taking into account specific conditions of the Romanian VVR-S Research Reactor. The Romanian VVR-S Research Reactor is an old reactor (1957) and its Decommissioning Plan is under study. The main topics of paper are as follows: Safety approach of nuclear facilities decommissioning. Applicable safety principles; Main steps of the proposed assessment methodology; Generic content of Decommissioning Plan. Main decommissioning activities. Discussion about the proposed Decommissioning Plan for Romanian Research Reactor; Safety risks which may occur during decommissioning activities. Normal decommissioning operations. Fault conditions. Internal and external hazards; Typical development of a scenario. Features, Events and Processes List. Exposure pathways. Calculation methodology. (author)

  9. Radiation research of materials using irradiation capsules

    International Nuclear Information System (INIS)

    Chamrad, B.

    1976-01-01

    The methods are briefly characterized of radiation experiments on the WWR-S research reactor. The irradiation capsule installed in the reactor including the electronic instrumentation is described. Irradiated samples temperature is stabilized by an auxiliary heat source placed in the irradiation space. The electronic control equipment of the system is automated. In irradiation experiments, experimental and operating conditions are recorded by a digital measuring centre with electric typewriter and paper tape data recording and by an analog compensating recorder. The irradiation experiment control system controls irradiated sample temperature, the supply current size and the heating element temperature of the auxiliary stabilizing source, inert and technological pressures of the capsule atmosphere and the thermostat temperature of the thermocouple junctions. (O.K.)

  10. Inelastic scattering of 275 keV neutrons by silver

    International Nuclear Information System (INIS)

    Litvinsky, L.L.; Zhigalov, Ya.A.; Krivenko, V.G.; Purtov, O.A.; Sabbagh, S.

    1997-01-01

    Neutron total, elastic and inelastic scattering cross-scattering of Ag at the E n = 275 KeV neutron energy were measured by using the filtered neutron beam of the WWR-M reactor in Kiev. The d-neutron strength function S n2 of Ag was determined from the analysis of all available data in the E n ≤ keV energy region on neutron inelastic scattering cross-sections with excitation of the first isomeric levels I π m = 7/2 + , E m ∼ 90 keV of 107,109 Ag: S n2 = (1.03 ± 0.19) · 10 -4 . (author). 10 refs, 3 figs

  11. Assessment of daily intake of major and trace elements by inhabitants of potential radiation protection of greater Cairo area, Egypt

    International Nuclear Information System (INIS)

    Ramadan, A.B.

    2005-01-01

    Concentrations of K, Ca, U, Th, Cs, Sr, I, Al, Cd, Cu, Mn, Pb, Ni and Cr were determined in vegetables, common foodstuffs and some animal products consumed by adult inhabitants of Greater Cairo Area. Some of these elements have chemical and biological similarity to some of the radionuclides abundantly encountered during nuclear power production and therefore data on these elements could provide important information on their biokinetic behavior. A total of 120 samples were analyzed using Neutron Activation Analysis (NAA) and Atomic Absorption Spectrometry (AAS). Generally, highest contributions for the intake of micro nutrients (Cu, Mn and Ni) arise from broad bean, rice and wheat flour consumption. Meat, milk, eggs and some vegetables are the major sources of K, Ca, U, Th, Cs, Al, Cd and Pb. The medium daily intake for the adult inhabitants of greater Cairo area was found to be 1.98 g of K, 0.54 mg of Ca, 1.14 fig of U, 0.8 μg of Th, 5.2μg of Cs, 1.3 mg of Sr, 105 μg of 1, 3.2 mg of Mn, 0.9 mg of Cu, 5.7 mg of Al, 5, 2 x 10 -2 mg of Pb, 2.1x10 -3 mg of Cd, 7.7x10 -2 mg of Ni and 2.1 x 10 -2 mg of Cr. The lower daily intake of Ca, Th, Cs and I by adult inhabitants of greater Cairo area could be due to the significantly lower consumption of milk and milk products, which are rich in these elements. The significantly lower intake of calcium by adult inhabitants of greater Cairo area may lead to higher uptake of radiostrontium and could result in higher internal radiation dose. The use of highly sensitive and reliable analytical methods resulted in accurate assessment of the values recorded for thorium and uranium suggested that radiation dose from their ingestion at natural background levels, is likely to be lower than those included in ICRP data. Concerning micro nutrients, the recommended values of daily intake of Cu and Mn are conveniently supplied by the common diet; however for Cr is lower than the recommended daily allowance. Due to high metals concentrations

  12. Innovation, adaptability, and collaboration: Keys to success for small and medium sized reactors. Cairo, 27 May 2001

    International Nuclear Information System (INIS)

    ElBaradei, M.

    2001-01-01

    Small and medium sized reactors, within a power output of less than 700 MW(e), are receiving increased consideration in the effort to meet changing market requirements. Smaller plants allow a more incremental investment, which can be used to hedge against demand uncertainty. They are more suitable for standardization and prefabrication, which in turn encourages enhanced quality control and stimulates rapid development of expertise and shorter construction schedules. They provide a better match to grid capacity in developing countries. And they are more easily adapted to a broad range of industrial settings and applications, such as district heating, heavy oil recovery, or the production of hydrogen and other chemical fuels. Sea water desalination is an application for which smaller reactors hold a particular advantage. Nuclear powered desalination is a proven technology. Clearly, we live in an era in which our society faces many difficult economic, environmental and social issues associated with sustainable development and energy demand. Against that backdrop, nuclear power is a mature technology that deserves careful consideration as a contributor to solving some of these issues. The development of innovative small and medium sized reactors will play a key role in helping to match state-of-the-art technology to user needs. An exchange of information and ideas is a step towards further progress

  13. Enhancement the physical protection system of the WWR-SM reactor at Institute of Nuclear Physics of Academy of Science of the Republic of Uzbekistan

    International Nuclear Information System (INIS)

    Karabaev, Kh.Kh.; Rakhimbaev, A.T.; Rakhmanov, A.B.; Salikhbaev, U.S.; Yuldashev, B.S.

    2004-01-01

    Full text: Joining of the Republic of Uzbekistan to Non-Proliferation Treaty required the revision of nuclear fuel protection system and radioactive sources from illegal access in all stages of work with nuclear materials. One of the primary technical actions of ensuring non-proliferation of nuclear materials is physical protection. The project was worked out on upgrading and enhancement of the physical protection of the reactor building. In cooperation with Sandia National Laboratory and support of the Department of Energy (DOE) USA The first stage of the physical protection upgrading provided for fresh fuel protection: - the new fresh fuel storage room was built and equipped with the modern control and detection system, - the reactor building was equipped with detection devices and access control, - the central alarm station (CAS) has been built and equipped with computer control and observing system, - code access system has been implemented. The first stage of upgrading of physical protection system was accomplished for 4 months, and put into operation in 1996. The second stage of physical protection system modernization included the construction of the second barrier of the physical protection, equipping it with observation and control devices and also extension of the CAS. The perimeter around the reactor building was cleaned from trees, bushed and in a short time a two-fence barrier was erected. The access control point provided the secured intensified control of the access to the reactor territory. The physical protection system was supplied with equipment for safeguard and TV observation of perimeter, access control to the territory of the reactor: - the CAS was extended and computer observation control system was upgraded, - the badge station has been constructed, equipped and set up, - all doors, windows, reactor hall gate have been replaced by strengthened metal ones, - uninterruptible power supply (UPS) and diesel-generator have been installed, - the

  14. Final report. U.S. Department of Energy University Reactor Sharing Program

    Energy Technology Data Exchange (ETDEWEB)

    Bernard, John A

    2003-01-21

    Activities supported at the MIT Nuclear Reactor Laboratory under the U.S. DOE University Reactor Sharing Program are reported for Grant DE FG02-95NE38121 (September 16, 1995 through May 31, 2002). These activities fell under four subcategories: support for research at thesis and post-doctoral levels, support for college-level laboratory exercises, support for reactor tours/lectures on nuclear energy, and support for science fair participants.

  15. Land Cover Mapping Analysis and Urban Growth Modelling Using Remote Sensing Techniques in Greater Cairo Region—Egypt

    Directory of Open Access Journals (Sweden)

    Yasmine Megahed

    2015-09-01

    Full Text Available This study modeled the urban growth in the Greater Cairo Region (GCR, one of the fastest growing mega cities in the world, using remote sensing data and ancillary data. Three land use land cover (LULC maps (1984, 2003 and 2014 were produced from satellite images by using Support Vector Machines (SVM. Then, land cover changes were detected by applying a high level mapping technique that combines binary maps (change/no-change and post classification comparison technique. The spatial and temporal urban growth patterns were analyzed using selected statistical metrics developed in the FRAGSTATS software. Major transitions to urban were modeled to predict the future scenarios for year 2025 using Land Change Modeler (LCM embedded in the IDRISI software. The model results, after validation, indicated that 14% of the vegetation and 4% of the desert in 2014 will be urbanized in 2025. The urban areas within a 5-km buffer around: the Great Pyramids, Islamic Cairo and Al-Baron Palace were calculated, highlighting an intense urbanization especially around the Pyramids; 28% in 2014 up to 40% in 2025. Knowing the current and estimated urbanization situation in GCR will help decision makers to adjust and develop new plans to achieve a sustainable development of urban areas and to protect the historical locations.

  16. Beyond the Bounds of the State: Reinterpreting Cairo’s Infrastructures of Mobility

    Directory of Open Access Journals (Sweden)

    Anna Rowell

    2018-06-01

    Full Text Available Mobility in Cairo is characterized by junctures of residents who redefine connectivity beyond the city’s spatial arrangements of tangible networks. This article presents Cairo as a mesh of invisible relations between material infrastructure, lives, and practices.  Egypt’s governing systems have, for many years, neglected to tackle inequality, particularly since the political turmoil of the January 2011 revolution. Cairo’s urban landscape is now one of fluctuating realities. Spates of laws prohibiting gatherings and committees, demographic neighbourhood shifts, uncontrolled urban growth, and arbitrary traffic and planning regulations have had palpable impacts on mobility patterns. This article shows that neoliberal spatial boundaries such as satellite compounds and large transport corridors have produced unequal relations of power and inclusivity. As marginalized citizens circumvent such boundaries and construct social solidarities to support their daily livelihoods, they reveal networks of resistance and subversion. Material infrastructures, deeply embedded in everyday politics and social relations, become key conceptual instruments in understanding how residents negotiate their freedoms in Cairo. Their ability to move from one sphere to another, whether social and cultural, or through a reinterpretation of public and private structures defines their right to the city outside formal governmental institutions.

  17. Calibration of a special neutron dosemeter based on solid-state track detectors and fission radiators in various neutron fields

    International Nuclear Information System (INIS)

    Doerschel, B.; Krusche, M.; Schuricht, V.

    1980-01-01

    The calibration of a personnel neutron dosemeter in different neutron fields is described. The badge-like dosemeter contains 5 detectors: polycarbonate foil (10 μm, Makrofol KG), 232 Th, natural uranium, natural uranium with boron, and natural uranium with cadmium. Detector sensitivity and calibration factors have been calculated and measured in radiation fields of 252 Cf fission neutrons, WWR-S reactor neutrons with and without Cd and Fe shielding, 3-MeV (d,t) generator neutrons, and 238 PuBe neutrons. Measurement range and achievable accuracy are discussed from the point of view of applying the dosemeter in routine and emergency uses

  18. U.S. uranium supply to the research and test reactor community

    International Nuclear Information System (INIS)

    Parker, Elaine M.

    2002-01-01

    From the 1950s through the early 1990s, the U.S. Department of Energy (DOE) was the primary supplier of low enriched uranium (LEU) and highly enriched uranium (HEU) to research and test reactors worldwide. The formerly called Y-12 Plant in Oak Ridge, Tennessee, was put into operational stand down in 1994 due to inadequate safety documentation. This paper will discuss the re-start of the Y-12 Plant and its current capabilities. Additionally, the paper will address recent changes within the DOE, with the creation of the National Nuclear Security Administration (NNSA). It will show how the change to NNSA and an organizational re-alignment has improved efficiencies. NNSA is committed to operate its sales program so that it is complementary to, and in support of, the Reduced Enrichment for Research and Test Reactors (RERTR) and Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Return Programs. The NNSA is committed to provide an assurance of competitively-priced, high-quality uranium supply to the research and test reactor community under long-term contracts. This paper will discuss some of NNSA's recent successes in long-term contracting and meeting deliveries. (author)

  19. A Walking Tour of Islamic Cairo: An Interactive Slide Lecture. Fulbright-Hays Summer Seminars Abroad Program, 2000 (Egypt and Israel).

    Science.gov (United States)

    Stanik, Joseph T.

    This curriculum project, a lesson on Islamic Cairo, could be used in a unit on Islamic civilization in an advanced placement high school world history or world civilization course, or it could be used in a college level Middle Eastern history or Islamic civilization course. Upon completion of the lesson, students will be able to describe in…

  20. Safe decommissioning of the Romanian VVR-S research reactor

    International Nuclear Information System (INIS)

    Garlea, C.; Garlea, I.; Kelerman, C.; Rodna, A.

    2002-01-01

    The VVR-S Romania research reactor was operated between 1957-1997, at 2 MW nominal power, for research and radioisotopical production. The detailed decommissioning plan was developed between 1995-1998, in the frame of the International Atomic Energy Agency Technical assistance project ROM/9/017. The proposed strategy agreed by the counterpart as well as international experts was stage 1. In 1997, an independent analysis performed by European Commission experts, in the frame of PHARE project PH04.1/1994 was dedicated to the 'Study of Soviet Design Research Reactors', had consolidated the development of the project emphasizing technical options of safe management for radioactive wastes and VVR-S spent fuel. The paper presents the main technical aspects as well as those of social impact, which lead to the establishment of strategy for safe management of decommissioning. Technical analysis of the VVR-S reactor and associated radwaste facilities (Radioactive Waste Treatment Plant - Magurele and National Repository Baita-Bihor) proved the possibility of the classical method utilization for dismantling of the facility and treatment-conditioning-disposal of the arrised wastes in safe conditions. The decommissioning plan at stage 2 has been developed based on radiological safety assessment, evaluation of radwaste inventory (removed as well as preserved on site), cost analysis and environmental impact. Technical data were provided by the R and D programme including neutron calculations and experiments, radiological characterizing (for facility and its influence area), seismic analysis and environmental balance during the operation and after shut down of the reactor. A special chapter is dedicated to regulatory issues concerning the development of decommissioning under nuclear safety. Based on the Fundamental Norms of Radiological Safety, the Regulatory Body defined the clearance levels and safety criteria for the process. The development of National Norms for the

  1. Development of the IAEA’s Knowledge Preservation Portals for Fast Reactors and Gas-Cooled Reactors Knowledge Preservation

    International Nuclear Information System (INIS)

    Batra, C.; Menahem, D. Beraha; Kriventsev, V.; Monti, S.; Reitsma, F.; Grosbois, J. de; Khoroshev, M.; Gladyshev, M.

    2016-01-01

    Full text: The IAEA has been carrying out a dedicated initiative on fast reactor knowledge preservation since 2003. The main objectives of the Fast Reactor Knowledge Portal (FRKP) initiative are to, a) halt the on-going loss of information related to fast reactors (FR), and b) collect, retrieve, preserve and make accessible existing data and information on FR. This portal will help in knowledge sharing, development, search and discovery, collaboration and communication of fast reactor related information. On similar lines a Gas Cooled Fast Reactor Knowledge Preservation portal project also started in 2013. Knowledge portals are capable to control and manage both publicly available as well as controlled information. The portals will not only incorporate existing set of knowledge and information, but will also provide a systemic platform for further preservation of new developments. It will include fast reactor and gas cooled reactor document repositories, project workspaces for the IAEA’s Coordinated Research Projects (CRPs), Technical Meetings (TMs), forums for discussion, etc. The portal will also integrate a taxonomy based search tool, which will help using new semantic search capabilities for improved conceptual retrieve of documents. The taxonomy complies with international web standards as defined by the W3C (World Wide Web Consortium). (author

  2. Preparation of Database for Land use Management in North East of Cairo

    International Nuclear Information System (INIS)

    El-Ghawaby, A.M.

    2012-01-01

    Environmental management in urban areas is difficult due to the amount and miscellaneous data needed for decision making. This amount of data is splendid without adequate database systems and modern methodologies. A geo-database building for East Cairo City Area (ECCA) is built to be used in the process of urban land-use suitability to achieve better performance compared with usual methods used. This Geo-database has required availability of detailed, accurate, updated and geographically referenced data on its terrain physical characteristics and its expected environmental hazards that may occur. A smart environmental suitability model for ECCA is developed and implemented using ERDAS IMAGINE 9.2. This model is capable of suggesting the more appropriate urban land-use, based on the existing spatial and non-spatial potentials and constraints.

  3. Concept, opportunities and challenges of urban tourism in the Arab world: Case studies of Dubai, Cairo and Amman

    OpenAIRE

    Al-Saad, Saad Ahmed; Ababneh, Abdelkader

    2017-01-01

    This paper aims to provide a better understanding of the current situation of urban tourism with referring to the experiences of the Arab World. By using bibliographic documentation and descriptive-analytic method, this paper addresses the main opportunities, impediments, and challenges of urban tourism in three Arab cities (Dubai, Cairo and Amman). This paper indicates that the three cities have many opportunities stemming from their location and their rich tourism resources. Moreover, urban...

  4. The Cairo conference and the assertion of sexual and reproductive rights a basis for sexual and reproductive health

    OpenAIRE

    Galdos Silva, Susana; Movimiento Manuela Ramos. Lima, Perú. Universidad Peruana Cayetano Heredia. Lima, Perú. Licenciada en educación, máster en salud pública, sexualidad y ciencias, MPH in Sexuality and Family Science.

    2014-01-01

    The article focuses on the International Conference on Population and Development held in El Cairo, Egypt, in 1994. The Conference addressed issues related to sexual and reproductive rights, actions to be adopted to improve the situation of young girls, the status of women, the situation of adolescents and gender equality as basic components to improve the sexual and reproductive health of the population. The concluding recommendations in this conference constitute the action program. This do...

  5. "Fossils" of practical medical knowledge from medieval Cairo.

    Science.gov (United States)

    Lev, Efraim; Amar, Zohar

    2008-09-02

    To asses the scientific value of the practical medical fragments found in the Cairo Genizah (10th century), as a useful source for ethnopharmacological purposes (in exposing rare and usually inaccessible original medieval practical knowledge of medicinal substances to present-day researchers), and to reconstruct the practical drugs and their uses. A methodology distinguishing between theoretical (about 1500 fragments) and practical medical knowledge (about 230 fragments) was created and used. The information regarding the practical medicinal substances was extracted from prescriptions (140), lists of drugs (70) and few letters of physicians. The reconstructed lists of practical (278) and theoretical (414) drugs allow us to recognize and quantify the gap between them in medieval times (136). We propose that the data obtained from ancient prescriptions is comparable to ethnopharmacological surveys. The finding of plants such as myrobalan, saffron, licorice, spikenard and lentisk, all of which have scientifically proven anti-microbial/bacterial and anti-fungal activity, sheds a helpful light on the medical decision-making of the medieval practitioners in respect of the plants they applied as drugs. With the wealth of information meticulously assembled from these time capsules we expect to make a significant contribution to contemporary efforts at locating modern drugs in ancient roots and gauging their feasibility.

  6. Studying Air Quality Dynamics using A Linear Genetic Programming Approach over Remotely Sensed Atmospheric Parameters: case study (Cairo, Egypt)

    Science.gov (United States)

    El-Askary, H. M.; Sheta, W.; Prasad, A. K.; Ali, H.; Abdel rahman, M.; El-Desouki, A.; Kafatos, M.

    2011-12-01

    For the past nine years starting from 2000, Cairo and the Delta region have been going through seriously high air pollution episodes that take place from October till November, locally known as the "Black Cloud". These temperature inversion episodes are attributed to Cairo's topography, complex climate systems, in addition to its economic growth and industrial activity and the long range transport from Europe. Carbon monoxide, ozone, methane, and water vapor are four major parameters that give an indication to the levels of pollution due to their interactions in the atmosphere. Carbon monoxide is especially an excellent tracer for pollution sources and pathways in the troposphere. The Nile Delta is known to be the most populous region of Egypt with major agricultural and industrial activities. The region suffers from intense episodes of natural and anthropogenic pollution especially during Spring (MAM), Summer (JJA), Fall (SON), and Winter (DJF) seasons. Previous studies found that the summer season shows long range transport of pollutants from Europe which is widely accepted. Recent studies attribute the local biomass burning in open fields to be the major culprit behind increased levels of pollution over major cities of the Delta region (such as Cairo) especially during the Fall season. Such episodes result in dense fog and haze which is locally known as "Black Cloud". We have analyzed multiple satellite datasets such as MODIS higher resolution daily aerosol parameters, vertical profiles from AIRS (meteorological and other parameters), HYSPLIT and GOCART models, and ground collected data (AOD, PM10, SO2 and NO2) to study the cause of Fall-time pollution over the Delta region. In this research we analysed aerosol, water vapor and cloud properties, over Cairo and the Greater Delta region starting from March 1st 2000 till May 31st 2010. The parameters involved in this analysis include nine parameters noted as P0 to P8 namely: Angstrom Exponent Land Mean, Atmospheric

  7. Treatment strategies in colorectal cancer patients with initially unresectable liver-only metastases, a study protocol of the randomised phase 3 CAIRO5 study of the Dutch Colorectal Cancer Group (DCCG)

    International Nuclear Information System (INIS)

    Huiskens, Joost; Gulik, Thomas M van; Lienden, Krijn P van; Engelbrecht, Marc RW; Meijer, Gerrit A; Grieken, Nicole CT van; Schriek, Jonne; Keijser, Astrid; Mol, Linda; Molenaar, I Quintus; Verhoef, Cornelis; Jong, Koert P de; Dejong, Kees HC; Kazemier, Geert; Ruers, Theo M; Wilt, Johanus HW de; Tinteren, Harm van; Punt, Cornelis JA

    2015-01-01

    Colorectal cancer patients with unresectable liver-only metastases may be cured after downsizing of metastases by neoadjuvant systemic therapy. However, the optimal neoadjuvant induction regimen has not been defined, and the lack of consensus on criteria for (un)resectability complicates the interpretation of published results. CAIRO5 is a multicentre, randomised, phase 3 clinical study. Colorectal cancer patients with initially unresectable liver-only metastases are eligible, and will not be selected for potential resectability. The (un)resectability status is prospectively assessed by a central panel consisting of at least one radiologist and three liver surgeons, according to predefined criteria. Tumours of included patients will be tested for RAS mutation status. Patients with RAS wild type tumours will be treated with doublet chemotherapy (FOLFOX or FOLFIRI) and randomised between the addition of either bevacizumab or panitumumab, and patients with RAS mutant tumours will be randomised between doublet chemotherapy (FOLFOX or FOLFIRI) plus bevacizumab or triple chemotherapy (FOLFOXIRI) plus bevacizumab. Radiological evaluation to assess conversion to resectability will be performed by the central panel, at an interval of two months. The primary study endpoint is median progression-free survival. Secondary endpoints are the R0/1 resection rate, median overall survival, response rate, toxicity, pathological response of resected lesions, postoperative morbidity, and correlation of baseline and follow-up evaluation with respect to outcomes by the central panel. CAIRO5 is a prospective multicentre trial that investigates the optimal systemic induction therapy for patients with initially unresectable, liver-only colorectal cancer metastases. CAIRO 5 is registered at European Clinical Trials Database (EudraCT) (2013-005435-24). CAIRO 5 is registered at ClinicalTrials.gov: NCT02162563, June 10, 2014

  8. Characterization of virulent Listeria monocytogenes isolates recovered from ready-to-eat meat products and consumers in Cairo, Egypt

    Directory of Open Access Journals (Sweden)

    Maysa A. I. Awadallah

    2014-10-01

    Full Text Available Aim: This study aimed to investigate the occurrence of some virulence genes distributed in Listeria monocytogenes isolated from ready-to-eat (RTE meat products and consumers in Cairo province, Egypt. Materials and Methods: A total of 120 beef luncheon, chicken luncheon and frankfurter beef (40 samples, each were collected from 10 different local shops situated in Al-salam city, Cairo province, Egypt. Stool samples were collected from 40 people who had the habit of consuming RTE meat. The suspected L. monocytogenes isolates were subjected to a multiplex polymerase chain reaction (PCR for rapid speciation and virulence determination using primers specific for inIA, inIC, and inIJ genes. Results: Culture examination of all samples on Oxford media revealed presence of colonies characteristic to L. monocytogenes in 6 beef luncheon (15%, 4 chicken luncheon (10%, 1 frankfurter beef (2.5% and 1 human stool (2.5% samples. Species identity of L. monocytogenes was verified through the amplification of a 800 bp fragment with inIA primers in 2 out of 6 culture isolates from beef luncheon (5%, and 1 out 4 culture isolates from chicken luncheon (2.5% samples. Statistical analysis revealed no significant difference between the occurrence of L. monocytogenes in different food samples examined (p>0.05. The virulence of these strains was ascertained by the presence of 517 bp and 238 bp fragments of inIC and inIJ genes, respectively in the isolates that contained the 800 bp fragment. The culture isolates obtained from one frankfurter beef sample, and one human stool sample were found negative by multiplex PCR for the presence of L. monocytogenes and its virulence specific genes. Conclusion: It could be concluded that L. monocytogenes are circulating in beef and chicken luncheon sold in Cairo, Egypt. Multiplex PCR is reliable for confirmation of L. monocytogenes. This study suggests the implementation of hygienic measures at all levels from production to consumption

  9. Geomechanical Investigations for Architectural Heritage Preservation. The Habib Sakakini Palace in Cairo, Egypt

    Directory of Open Access Journals (Sweden)

    Sayed HEMEDA

    2013-03-01

    Full Text Available The understanding of the geotechnical problems and failure mechanisms of stone structures of Sakakini palace (1897 AC entails a comprehensive study on the mechanical behavior of the stones and other construction materials. In addition to micro analysis, geological and geomorphologic interests, several investigations on stone deterioration and engineering geology were performed. First phase included more advanced techniques, which provided additional information on particular aspects of site deterioration and it included laser analysis (LIBS, electron probe micro analysis, micro XRD and XRF analyses, scanning electron microscope analysis coupled with EDX probing, transmission electron microscopy and grain size distribution analysis, permeability and pore size distribution of stone, mortars, core binders and other construction materials. Second phase included the determination of mechanical properties of building stones, such as compressive strength, modulus of elasticity, tensile strength, and shear strength. To obtain reliable values for these properties, a suitable number of samples should be extracted, prepared for testing, and properly tested. The test results are then analyzed to establish the investigated stone properties. The testing program includes extracting seven cylindrical cores from the basement stone walls of Sakakini’s mansion in down town Cairo. The objectives of the study are to provide a characterization of micro structures and the mechanical properties of the stones of Sakakini’s Mansion; The purpose of the present research is to provide recommendations regarding the strengthening and the safety of architectural heritage under long and short-term loading. For this purpose, a set of experimental tests and of advanced numerical analyses are to be carried out.

  10. U. S. Utility Leadership in Requirements For Passive Reactors

    International Nuclear Information System (INIS)

    Kim, Jcng H.; Layman, William H.

    1991-01-01

    Utility leadership from both U.S. utilities and international utilities, is a key element in the U. S. Advanced Light Water Reactor Program. International utilities have played a very import Design reviews by the utilities participating in the ALRR Program will ensure that all of the utility requirements are met while design work is being carried out. Our mission is to achieve NRC certification of designs that reflect the needs of the utilities and we believe that this will play an important role in the resurgence of nuclear plant construction in the United States. As stated in the Nuclear Power Oversight Committee's Strategic Plan For Building New Nuclear Power Plants : 'The extensive operating experience with today's light water reactors (LWRs), and the promise shown in recent technical developments, leads the industry to the conclusion that the next nuclear plants ordered in the United States will be advanced light water reactors (A LWRs). Two types are under development : units of large output (1300 MW) called 'evolutionary' A LWRs and units of mid-size output (600 MW) called 'Passive' A LWRs. The term 'passive' refers to the safety features which depend more on natural processes such as gravity and buoyancy than on powered equipment such as pumps

  11. Current status of operation and utilization of the Dalat Research Reactor

    International Nuclear Information System (INIS)

    Dien, Nguyen Nhi

    2006-01-01

    The Dalat Nuclear Research Reactor (DNRR) is a 500 kW pool-type reactor using the HEU (36% enrichment) WWR-M2 fuel assemblies. It was renovated and upgraded from the USA 250 kW TRIGA Mark-II reactor. The first criticality of the renovated reactor was in the 1st November 1983 and its regular operation at nominal power of 500 kW has been since March 1984. The DNRR is operated mainly in continuous runs of 100 hrs, once every 4 weeks, for radioisotope production, neutron activation analysis, scientific research and training. The remaining time between two continuous runs is devoted to maintenance activities and also to short run for reactor physics and thermal hydraulics experiments. From the first start-up to the end of December 2004, it totaled about 27,253 hrs of operation and the total energy released was about 543 MWd. The first fuel reloading was executed in April 1994 after more than 10 years of operation with 89 fuel assemblies (FA). The 11 new FAs were added in the core periphery, at previous beryllium element locations. After reloading the working configuration of reactor core consisted of 100 FAs. The second fuel reloading was executed in March 2002. The 4 new FAs were added in the core periphery, at previous beryllium element locations. The working configuration of 104 FAs ensured efficient exploitation of the DNRR at nominal power for about 3000 hrs since March 2002. In order to provide excess reactivity for the reactor operation without the need to discharge high burned FAs, in June 2004, the fuel shuffling of the reactor core was done. 16 FAs with low burn-up from the core periphery were moved toward the core center and 16 FAs with high-burn-up from the core center were moved toward the core periphery. This operation provided additional reactivity of about 0.85 β eff that the current reactor configuration using re-shuffled HEU fuel is expected to allow normal operation until June 2006. In 1999, the request of returning to Russia HEU fuels from foreign

  12. Full instantaneous traversal rupture of the primary loop pipeline

    International Nuclear Information System (INIS)

    Baytelesov, S.A.; Kungurov, F.R.

    2010-01-01

    Accident, reflecting full immediate cross rupture of primary loop pipe of WWR-SM research reactor of INP AS RUz is observed in this paper. Calculations for accident situation and analysis for different reactor cores, formed from fully IRT-3M type high enriched fuel (36% enrichment on 235 U), first mixed core, compiled from 16 IRT-3M fuel assemblies and 4 IRT-4M type fuel assemblies with low enriched fuel (19,7% enrichment on 235 U) and the core fully formed from low enriched fuel are carried out

  13. Ahead with Cairo. Monitoring country activities.

    Science.gov (United States)

    Danguilan, M; Wainer, J; Widyantoro, N; Capoor, I; Huq, N; Ashino, Y; Sadasivam, B; Le Thi Nham Tuyet

    1995-04-01

    In the aftermath of the 1994 UN Conference on Population and Development (ICPD) in Cairo, countries are proceeding with their implementation of the plan of action adopted at the conference. A brief description is given of some actions taken by specific countries toward plan implementation. In the Philippines meetings were held immediately after the conference in October on the implications for the Management, Family Planning, and Nongovernmental Organizations programs. The issues of concern were identified as the need for regular consultative meetings among relevant agencies, consultations with women's groups, and a responsive adolescents program. In Australia the program thrust was to focus on the implications for immigration. Monitoring of the plans of action will be undertaken by nongovernmental organizations (NGOs). In Malaysia committees are preparing a program of action suitable for implementation in Malaysia. A regional women's NGO organized a forum on the implications of ICPD for women's reproductive health, women's rights, and empowerment in Malaysia. In Vietnam, press conferences are used to communicate conference results. An NGO translated relevant ICPD materials into Vietnamese. In Indonesia, several ministries convened meetings among donors, NGOs, women's groups, and experts. In India, the government held a national conference. One view was that population issues should be discussed in the context of gender equality and empowerment of women. Another issue was the importance of placing reproductive health in the larger context of health and primary health services. Health personnel at all levels were considered in need of sensitization on gender issues. Problems such as anemia have not been successfully addressed in existing programs. The government agreed to remove in phases target driven programs and the sterilization emphasis. In Bangladesh, a national committee was formed, and NGOs are actively distributing information. In Japan, the Family Planning

  14. Mulk Raj Anand's Punjab Trilogy and Naguib Mahfouz's Cairo Trilogy: A Comparative Study

    Directory of Open Access Journals (Sweden)

    Abdulrahman Mokbel Mahyoub Hezam

    2016-01-01

    Full Text Available Writing about Mulk Raj Anand, Indian writer, and Naguib Mahfouz, Egyptian writer, is writing about two of the great writers who played major roles in developing the novel in their own countries. They succeeded in using novel to deal with the historical development in their respective societies. This study examines two of their best-known works Punjab Trilogy and Cairo trilogy. This paper investigates the way Anand and Mahfouz accomplish their construction of private and public lives and how they try to show a large picture of the society through the private lives of their characters. The significance of the study lies in comparing two great writers of two great nations that underwent similar historical development in the first half of the 20th century. Keywords: Comparative study, Egypt, history, India, Trilogy

  15. A Small Modular Reactor Design for Multiple Energy Applications: HTR50S

    Energy Technology Data Exchange (ETDEWEB)

    Yan, X.; Tachibana, Y.; Ohashi, H.; Sato, H.; Tazawa, Y.; Kunitomi, K. [Japan Atomic Energy Agency, Ibaraki (Japan)

    2013-06-15

    HTR50S is a small modular reactor system based on HTGR. It is designed for a triad of applications to be implemented in successive stages. In the first stage, a base plant for heat and power is constructed of the fuel proven in JAEA's 950 .deg. C, 30MWt test reactor HTTR and a conventional steam turbine to minimize development risk. While the outlet temperature is lowered to 750 .deg. C for the steam turbine, thermal power is raised to 50MWt by enabling 40% greater power density in 20% taller core than the HTTR. However the fuel temperature limit and reactor pressure vessel diameter are kept. In second stage, a new fuel that is currently under development at JAEA will allow the core outlet temperature to be raised to 900 .deg. C for the purpose of demonstrating more efficient gas turbine power generation and high temperature heat supply. The third stage adds a demonstration of nuclear-heated hydrogen production by a thermochemical process. A licensing approach to coupling high temperature industrial process to nuclear reactor will be developed. The low initial risk and the high longer-term potential for performance expansion attract development of the HTR50S as a multipurpose industrial or distributed energy source.

  16. The Cairo conference: feminists vs. the Pope.

    Science.gov (United States)

    Grant, L

    1994-07-01

    The draft Programme of Action to be discussed at the UN International Conference on Population and Development (ICPD) in Cairo is not about population and development, but about women and related agendas, supporting the various family forms (which promote population growth), and incalculable amounts of funding to increase the breadth of goals (e.g., more funding to improve the quality of life in cities). It does little to link those goals with global population growth. The US Department of State supports the militant feminists' agenda, which is for money to be directed to women's advancement activities rather than to direct population programs. Their reasoning is that women will achieve the socially desirable fertility level if they have unimpeded freedom of choice. The Vatican, which opposes birth control and abortion, is chastising the women's groups and the population movement. The US government has shifted its position to accommodate the militant feminists. It is not listening to bioscientists, demographers, and others who might have mellowed the advocacy approach. The draft Programme of Action has no population goals, which are needed to operate a population program. The US government should call for meeting unmet needs for contraception, expansion of family planning facilities and services in developing countries, and reinstatement of goals in the international population dialogue. It should also continue efforts to persuade developing country leaders of the importance of the population issue and of incentives and disincentives. Its first priority should be population, followed by development assistance to maternal and child health services coordinated with family planning services.

  17. Computer control system synthesis for nuclear power plants through simplification and partitioning of the complex system model into a set of simple subsystems

    International Nuclear Information System (INIS)

    Zobor, E.

    1978-12-01

    The approach chosen is based on the hierarchical control systems theory, however, the fundamentals of other approaches such as the systems simplification and systems partitioning are briefly summarized for introducing the problems associated with the control of large scale systems. The concept of a hierarchical control system acting in broad variety of operating conditions is developed and some practical extensions to the hierarchical control system approach e.g. subsystems measured and controlled with different rates, control of the partial state vector, coordination for autoregressive models etc. are given. Throughout the work the WWR-SM research reactor of the Institute has been taken as a guiding example and simple methods for the identification of the model parameters from a reactor start-up are discussed. Using the PROHYS digital simulation program elaborated in the course of the present research, detailed simulation studies were carried out for investigating the performance of a control system based on the concept and algorithms developed. In order to give a real application evidence, a short description is finally given about the closed-loop computer control system installed - in the framework of a project supported by the Hungarian State Office for Technical Development - at the WWR-SM research reactor where the results obtained in the present IAEA Research Contract were successfully applied and furnished the expected high performance

  18. Nuclear reactor safety program in U.S. Department of Energy and future perspectives

    International Nuclear Information System (INIS)

    Song, Y.T.

    1987-01-01

    The U.S. Department of Energy (DOE) establishes policy, issues orders, and assures compliance with requirements. The contractors who design, construct, modify, operate, maintain and decommission DOE reactors, set forth the assessment of the safety of cognizant reactors and impliment DOE orders. Teams of experts in the Depatment, through scheduled and unscheduled review programs, reassess the safety of reactors in every phases of their lives. As new technology develops, the safety programs are reevaluated and policies are modified to accommodate these new technologies. The diagnostic capabilities of the computer using multiple alarms to enhance detection of defects and control of a reactor have been greatly utilized in reactor operating systems. The application of artificial intelligence (AI) technologies for diagnostic and even for the decision making process in the event of reactor accidents would be one of the future trends in reactor safety programs. (author)

  19. Final report on the IAEA research contracts No. 1194/RB, 1194/R1/RB and 1194/R2/RB

    International Nuclear Information System (INIS)

    Zobor, E.; Janosy, J.S.; Szentgali, A.

    1980-09-01

    The final report summarizes the research activities made in the framework of the IAEA Research Contracts No. 1194/RB, 1194/R1/RB and 1194/R2/RB. A multilevel hierarchical control system is treated which uses weakly-coupled low dimensional subsystems under the supervision of a dynamic coordinator program. This self-organizing adaptive control system was checked by a 5 MW research reactor. As an example the paper describes the experimental computer control system of the 5 MW WWR-SM research reactor, where the reactor power and outlet temperature have been controlled on the basis of the treated control concept since 1978. (author)

  20. Preliminary Design of S-CO2 Brayton Cycle for KAIST Micro Modular Reactor

    International Nuclear Information System (INIS)

    Kim, Seong Gu; Kim, Min Gil; Bae, Seong Jun; Lee, Jeong Ik

    2013-01-01

    This paper suggests a complete modular reactor with an innovative concept of reactor cooling by using a supercritical carbon dioxide directly. Authors propose the supercritical CO 2 Brayton cycle (S-CO 2 cycle) as a power conversion system to achieve small volume of power conversion unit (PCU) and to contain the core and PCU in one vessel for the full modularization. This study suggests a conceptual design of small modular reactor including PCU which is named as KAIST Micro Modular Reactor (MMR). As a part of ongoing research of conceptual design of KAIST MMR, preliminary design of power generation cycle was performed in this study. Since the targets of MMR are full modularization of a reactor system with S-CO 2 coolant, authors selected a simple recuperated S-CO 2 Brayton cycle as a power conversion system for KAIST MMR. The size of components of the S-CO 2 cycle is much smaller than existing helium Brayton cycle and steam Rankine cycle, and whole power conversion system can be contained with core and safety system in one containment vessel. From the investigation of the power conversion cycle, recompressing recuperated cycle showed higher efficiency than the simple recuperated cycle. However the volume of heat exchanger for recompressing cycle is too large so more space will be occupied by heat exchanger in the recompressing cycle than the simple recuperated cycle. Thus, authors consider that the simple recuperated cycle is more suitable for MMR. More research for the KAIST MMR will be followed in the future and detailed information of reactor core and safety system will be developed down the road. More refined cycle layout and design of turbomachinery and heat exchanger will be performed in the future study

  1. Analysis of aeromagnetic data for interpretation of seismicity at Fayoum-Cairo area, Egypt

    Directory of Open Access Journals (Sweden)

    Ahmed Bakr Khalil

    2014-01-01

    Full Text Available An aeromagnetic reconnaissance study is presented to delineate the subsurface structure and tectonic setting at the Fayoum-Cairo district, which experienced a damaging earthquake on October 12, 1992 of magnitude (M = 5.7. Analysis of aeromagnetic and seismicity data demonstrate three significant tectonic faults with trending to the NE-SW, NW-SE and E-W. The basement is uplifted in the northern and central parts with a depth of 1.3 km, and deepening in the southern part with a depth of 2.5 km. This is a seismically active zone and historically has experienced damaging earthquakes. In 1847, a damaging earthquake with maximum epicentral intensity (Modified Mercalli Intensity (MMI = VII was located there. On the eastern side, earthquake sources are well recognized at different locations. These sources created events of moderate size magnitude M < 5. The focal mechanisms of the major events from these sources are generally strike-slip with normal component. The focal mechanism of the earthquake on October 12, 1992 is normal fault type with strike trends in the NW-SE direction. These fault plane solutions are consistent with the tectonic trends derived from the aeromagnetic data mentioned above and suggest that the new tectonics of northeast Africa is predominant.     Resumen   Este estudio presenta una exploración aeromagnética para delimitar la estructura subsuperficial y el marco tectónico del distrito de Fayoum-Cairo, que sufrió un terremoto el 12 de octubre de 1992 de magnitud M=5.7. Los análisis de datos sismicidad y aeromagnéticos señalan tres fallas tectónicas significativas con tendencias NE-SO, NO-SE y E-O. El subsuelo se elevó en el norte y en el centro a una profundidad de 1,3 kilómetros, y se hundió en el sur con una profundidad de 2,5 kilómetros. Esta es una zona sísmicamente activa que en su historia ha tenido terremotos dañinos. En 1847 tuvo lugar un terremoto con intensidad epicentral máxima (escala sismológica de

  2. Environmental and Occupational Lead Exposure Among Children in Cairo, Egypt: A Community-Based Cross-Sectional Study.

    Science.gov (United States)

    Moawad, Eman Mohamed Ibraheim; Badawy, Nashwa Mostafa; Manawill, Marie

    2016-03-01

    The aim of this study was to assess childhood lead exposure in a representative sample of Cairo, and to investigate the possible risk factors and sources of exposure. This cross-sectional study was conducted from November 2014 through April 2015. The target population was children aged 6 to 18 years, recruited into 4 groups, garbage city, moderate-living standard area, urban and suburban schools, and workshops in the city of Cairo. Blood lead levels (BLLs) and hemoglobin (Hb) concentrations were measured. Also, potential local environmental sources were assessed for hazardous lead contamination. Analysis on 400 participants has been carried out. A total of 113 children had BLLs in the range 10 to 20 μg/dL. Smoking fathers, housing conditions, playing outdoors, and exposure to lead in residential areas were significantly correlated with high BLLs. The mean values of hemoglobin were inversely correlated with BLLs. Children involved in pottery workshops had the highest BLLs and the lowest Hb values with a mean of (43.3 μg/dL and 8.6 g/dL, respectively). The mean value of environmental lead in workshop areas exceeded the recommended levels. Also, those values measured in dust and paint samples of garbage city were significantly high. Moreover, the mean lead levels in the soil samples were significantly higher in urban schools (P = 0.03) than the suburban ones. Childhood lead poisoning accounts for a substantial burden in Egypt, which could be preventable. Development of national prevention programs including universal screening program should be designed to reduce incidence of lead toxicity among children.

  3. Radiological protection of the staff during the decommissioning operations of the Romanian VVR-S research reactor

    International Nuclear Information System (INIS)

    Ene, D.C.

    2002-01-01

    Dose rate estimates for periods of 100 days and 6, 10, 25, 100 years after the shut down of the Romanian VVR-S reactor are presented in this paper for some foreseen decommissioning activities which include: i) cutting the water pipe in the pump room and the reactor sealing operations; ii) extracting reactor components; and iii) handling and dismantling the internal structures taken of from the reactor. For the reactor components extracted from the reactor, the considered calculation points were placed in the central plan of the items, on the surface and at distances from the surface which correspond to +0.2m, +1m, +2m, +8m, and +10m. Time dependence of the resulted dose rates are presented and discussed. Qualitative comparison with the measured values from other VVR-S reactors is done. The obtained results assist to develop working procedures that must be observed during the decommissioning activities. (author)

  4. U.S. Non-proliferation policy and programs regarding use of high-enriched uranium in research reactors

    International Nuclear Information System (INIS)

    Lewis, R.A.

    1993-01-01

    Uranium enriched to 90-93%, supplied by the U.S., is now used in 141 research and test reactors in 35 countries around the world with a cumulative power of 1714 mw. Since of the order of 3 kg of 235 U is involved annually in fuel fabrication, fresh fuel transport and storage, reactor operation, and spent fuel cooling and return per megawatt of research reactor power, it is estimated that more than 5000 kg of very high-enriched uranium is handled each year to operate these reactors. Recent U.S. assessments have led to the tentative conclusion that in only approximately 11 of these reactors, generally those of highest power or power density, is the use of 90-93% enriched uranium currently a technical necessity. Universal use of the best state-of-the-art fuel technology would permit an estimated 90 of these reactors to use 20% enriched fuel, and estimated 40 others to use 45% enriched fuel, without significant performance degradation. If advanced research reactor fuel development programs currently under way in the U.S. and elsewhere are successful, it may, in fact, be possible to operate virtually all of these reactors on less than 20% enriched uranium in the longer term. The physical and economic practicality of these developmental fuels must, of course, await future assessments

  5. THE EFFECT OF THE WINDOW-TO-WALL RATIO ON COOLING ENERGY USAGE AND COMFORT TEMPERATURE

    Directory of Open Access Journals (Sweden)

    Aris Budhiyanto

    2017-12-01

    Full Text Available This study presents an investigation of the effect of building envelope, especially glass facade buildings on cooling energy usage and thermal comfort. An office building was modeled with various window-to-wall ratio (WWR using panasap glass with SC=0.58 in order to analyze the effect of the WWR addition on cooling energy usage and comfort temperature. The result suggested that the average increase of the cooling energy usage is about 5.67% per 10% WWR addition, and of the operative temperature ranges from 0.350C to 0.560C per 10% WWR addition. Moreover, the building with above 20% WWR doesn’t provide comfort temperature.

  6. Experience in incorporation control of operation personnel of the Reinsberg nuclear power plant (1967 - 1973)

    International Nuclear Information System (INIS)

    Pul'khajm, K.F.; Klyuke, Kh.

    1976-01-01

    A theoretic estimate of fission products and corrosion nuclides in a WWR type reactor is given. The results of radiation monitoring of the personnel irradiation at the Reinsberg (DDR) nuclear power plant are presented. It is supposed that the intake of fission and corrosion products has been realized through inhalation. The equivalent doses of internal irradiation are calculated. The estimate of the results of radiation monitoring are presented [ru

  7. In-Pile Assemblies for Investigation of Tritium Release from Li2TiO3 Lithium Ceramic

    International Nuclear Information System (INIS)

    Shestakov, V.; Tazhibayeva, I.; Kawamura, H.; Kenzhin, Y.; Kulsartov, T.; Chikhray, Y.; Kolbaenkov, A.; Arinkin, F.; Gizatulin, Sh.; Chakrov, P.

    2005-01-01

    The description of algorithm to design in-pipe experimental ampoule devices (IPAD) is presented here, including description of IPAD design for irradiation tests of highly enriched lithium ceramics at WWR-K reactor. The description of the system for registration of tritium release from ceramics during irradiation is presented as well. Typical curve of tritium release from the IPAD during irradiation under various temperatures of the samples is shown here

  8. Advanced liquid metal reactor development at Argonne National Laboratory during the 1980s

    International Nuclear Information System (INIS)

    Wade, D.C.

    1990-01-01

    Argonne National Laboratory's (ANL'S) effort to pursue the exploitation of liquid metal cooled reactor (LMR) characteristics has given rise to the Integral Fast Reactor (IFR) concept, and has produced substantial technical advancement in concept implementation which includes demonstration of high burnup capability of metallic fuel, demonstration of injection casting fabrication, integral demonstration of passive safety response, and technical feasibility of pyroprocessing. The first half decade of the 90's will host demonstration of the IFR closed fuel cycle technology at the prototype scale. The EBR-II reactor will be fueled with ternary alloy fuel in HT-9 cladding and ducts, and pyroprocessing and injection casting refabrication of EBR-II fuel will be conducted using near-commercial sized equipment at the Fuel cycle Facility (FCF) which is co-located adjacent to EBR-II. Demonstration will start in 1992. The demonstration of passive safety response achievable with the IFR design concept, (already done in EBR-II in 1986) will be repeated in the mid 90's using the IFR prototype recycle fuel from the FCF. The demonstration of scrubbing of the reprocessing fission product waste stream, with recycle of the transuranics to the reactor for consumption, will also occur in the mid 90's. 30 refs

  9. Numerical modelling evaluation for the microclimate of an outdoor urban form in Cairo, Egypt

    Directory of Open Access Journals (Sweden)

    Mohamed H. Elnabawi

    2015-08-01

    Full Text Available In order to achieve outdoor thermal comfort it is necessary to understand the interactions between the prevailing climate, the urban form and roughness. The near surface boundary layer is directly influenced by local irradiative and convective exchange processes due to the presence of a variety of different surfaces, sheltering elements and obstacles to air flow leading to distinctive micro-scale climates. The paper presents a micro-scale numerical model for an outdoor urban form for a hot summer’s day in Al-Muizz street located at the Islamic quarter of Cairo, where a few studies have attempted to study these conditions in vernacular settings in hot arid areas where the continuously evolving urban patterns and shaded environments were perceived to produce more pedestrian friendly outdoor environments. In situ measurements are used to validate the ENVI-met results which showed an overall agreement with the observed ones, representing adequate mean radiant temperature (Tmrt which is one of the most important meteorological parameters governing human energy balance and has therefore a strong influence on thermal sensation of the pedestrians using the open public spaces and generating a micro-climatic map as an initial step in addressing the urgent need for a modelling platform accessible to urban designers, architects, and decision makers towards sustainable urban forms.

  10. Experimental validation of TASS/SMR-S critical flow model for the integral reactor SMART

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Si Won; Ra, In Sik; Kim, Kun Yeup [ACT Co., Daejeon (Korea, Republic of); Chung, Young Jong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2011-05-15

    An advanced integral PWR, SMART (System- Integrated Modular Advanced ReacTor) is being developed in KAERI. It has a compact size and a relatively small power rating (330MWt) compared to a conventional reactor. Because new concepts are applied to SMART, an experimental and analytical validation is necessary for the safety evaluation of SMART. The analytical safety validation is being accomplished by a safety analysis code for an integral reactor, TASS/SMR-S developed by KAERI. TASS/SMR-S uses a lumped parameter one dimensional node and path modeling for the thermal hydraulic calculation and it uses point kinetics for the reactor power calculation. It has models for a general usage such as a core heat transfer model, a wall heat structure model, a critical flow model, component models, and it also has many SMART specific models such as an once through helical coiled steam generator model, and a condensate heat transfer model. To ensure that the TASS/SMR-S code has the calculation capability for the safety evaluation of SMART, the code should be validated for the specific models with the separate effect test experimental results. In this study, TASS/SMR-S critical flow model is evaluated as compared with SMD (Super Moby Dick) experiment

  11. Evidence of infection with avian, human, and swine influenza viruses in pigs in Cairo, Egypt.

    Science.gov (United States)

    Gomaa, Mokhtar R; Kandeil, Ahmed; El-Shesheny, Rabeh; Shehata, Mahmoud M; McKenzie, Pamela P; Webby, Richard J; Ali, Mohamed A; Kayali, Ghazi

    2018-02-01

    The majority of the Egyptian swine population was culled in the aftermath of the 2009 H1N1 pandemic, but small-scale growing remains. We sampled pigs from piggeries and an abattoir in Cairo. We found virological evidence of infection with avian H9N2 and H5N1 viruses as well as human pandemic H1N1 influenza virus. Serological evidence suggested previous exposure to avian H5N1 and H9N2, human pandemic H1N1, and swine avian-like and human-like viruses. This raises concern about potential reassortment of influenza viruses in pigs and highlights the need for better control and prevention of influenza virus infection in pigs.

  12. Quality control of baby food products on the basis of results obtained using the instrumental neutron-activation analysis technique

    International Nuclear Information System (INIS)

    Mukhammedov, S.; Khaydarov, A.; Pardaev, O.

    2013-01-01

    The purpose of this study was to use the instrumental neutron-activation analysis (INAA) to determine the elemental composition of some kind of imported baby food products (BFP) and to compare the results with the permissible contents. The nuclear reactor WWR-SM of INP has been used to develop INAA to study the mineral composition of some children's food products. The concentration of 26 trace elements, including Mg, Ca, Fe, Zn, etc. was found. The comparison of the results with regulation contents and the daily data on food needs have shown that the investigated group of BFP does not meet the requirements for all trace and macro elements composition. (authors)

  13. Geochemical characteristics of black shales from the ore-bearing complex of strata of the Male Karpaty Mts. IV. Evaluation of data on the element contents obtained by neutron activation analysis

    Energy Technology Data Exchange (ETDEWEB)

    Cambel, B. (Slovenska Akademia Vied, Bratislava (Czechoslovakia). Geologicky Ustav); Khun, M. (Komenskeho Univ., Bratislava (Czechoslovakia). Prirodovedecka Fakulta)

    1983-06-01

    The application is described of instrumental neutron activation analysis in determining the levels of the individual elements in rocks. Samples were irradiated in the WWR-S reactor at Rez near Prague, and evaluated by the Radiometric Department of the Central Laboratories of the Czechoslovak Uranium Industry. The results are described in detail of measuring the levels of W, Ta, Sc, Hf, Ga, Rb, Cs, U, Th, Au, Sb, As, Zn and Ag in Male Karpaty rocks. The levels of the elements in different samples and in different localities are tabulated. A comparison is made with the Keno Hill, Yukon (USA) area where the polymetallic mineralization is evolutionally analogous to that of the Male Karpaty region.

  14. Geochemical characteristics of black shales from the ore-bearing complex of strata of the Male Karpaty Mts

    International Nuclear Information System (INIS)

    Cambel, B.; Khun, M.

    1983-01-01

    The application is described of instrumental neutron activation analysis in determining the levels of the individual elements in rocks. Samples were irradiated in the WWR-S reactor at Rez near Prague, and evaluated by the Radiometric Department of the Central Laboratories of the Czechoslovak Uranium Industry. The results are described in detail of measuring the levels of W, Ta, Sc, Hf, Ga, Rb, Cs, U, Th, Au, Sb, As, Zn and Ag in Male Karpaty rocks. The levels of the elements in different samples and in different localities are tabulated. A comparison is made with the Keno Hill, Yukon (USA) area where the polymetallic mineralization is evolutionally analogous to that of the Male Karpaty region. (M.D.)

  15. Nuclear prehistory influence on transfer velocity of 54Mn impurity 'hot' atoms in irradiated metallic iron

    International Nuclear Information System (INIS)

    Alekseev, I.E.

    2007-01-01

    Influence of nuclear prehistory on transfer velocity of 54 Mn impurity 'hot'-atoms - got by different nuclear channels: 56 Fe(d, α), 54 Fe(n,p) in irradiated metallic iron - is studied. Irradiation of targets were carried out in U-120 accelerator (energy range 7.3/5.3 MeV, deuteron beam current makes up 5 μA). Mean density of thermal neutron (WWR-M reactor) makes up 8.6·10 13 neutron·cm -2 ·s -1 . It is shown, that transfer velocity of 54 Mn 'hot' atoms is defining by rate of radiation damage of targets in the irradiation process at that a key importance has a bombarding particles type applied for radioactive label getting

  16. Eugene P. Wigner’s Visionary Contributions to Generations-I through IV Fission Reactors

    Directory of Open Access Journals (Sweden)

    Carré Frank

    2014-01-01

    Full Text Available Among Europe’s greatest scientists who fled to Britain and America in the 1930s, Eugene P. Wigner made instrumental advances in reactor physics, reactor design and technology, and spent nuclear fuel processing for both purposes of developing atomic weapons during world-war II and nuclear power afterwards. Wigner who had training in chemical engineering and self-education in physics first gained recognition for his remarkable articles and books on applications of Group theory to Quantum mechanics, Solid state physics and other topics that opened new branches of Physics.

  17. Viaje póstumo a París del Faraón Ramsés II

    Directory of Open Access Journals (Sweden)

    Esteban Llagostera

    2010-01-01

    Full Text Available Por primera vez en la historia, un faraón egipcio viaja al extranjero. Su momia, fue trasladada a París, para «curarla» de las múltiples invasiones de bacterias, insectos necrófagos, microbios y hongos de los que estaba invadido, además de múltiples fracturas. E igualmente, para diagnosticar las causas de su muerte. El traslado de El Cairo a París y regreso, se realizó con un avión militar francés. Egipto, notificó a Israel este vuelo extraordinario, para evitar cualquier problema que pudiera surgir, en aquella zona tan conflictiva de Oriente Medio. En cuanto el avión penetro en el espacio aéreo francés, dos reactores militares le dieron escolta hasta el aeropuerto de Le Bourget-París, donde se le rindieron honores de Jefe de Estado. Toda Francia se puso a disposición de Ramsés el Grande. Mme. Desroches- Noblecourt, Inspectora General a Perpetuidad de los Museos Estatales de Francia, no lo abandonó ni un momento y voló con él desde Heliopolis hasta París y su posterior regreso a El Cairo.When French scientists informed Mme. Desroches-Noblecourt, Inspector General of National Museums, of the poor state of preservation of the mummy of pharaoh Ramesses II (he suffered from bacteria, necrophagus insects, fungus, etc., she immediately informed the President of France, who made a quick trip to inform the Egyptian President about the news. Giscard d’Estaing suggested taking the mummy to Paris in a special plane. Due to the political situation of the time and because Ramesses II would be travelling in a military plane, Egypt informed Israel about the special conditions surrounding this extraordinary flight. This was to be the first time in History that an Egyptian pharaoh «travelled» to a foreign country. The plane departed from Cairo’s Heliopolis Airport where the royal passenger was treated to the honours of a living king. The date was September 26th, 1976. The moment the plane entered French air space; two air force

  18. Nuclear science. U.S. electricity needs and DOE's civilian reactor development program

    International Nuclear Information System (INIS)

    England-Joseph, Judy; Allen, Robert E. Jr.; Fitzgerald, Duane; Young, Edward E. Jr.; Leavens, William P.; Bell, Jacqueline

    1990-05-01

    Electricity projections developed by the North American Electric Reliability Council (NERC) appear to be the best available estimates of future U.S. electricity needs. NERC, which represents all segments of the utility industry, forecasts that before 1998 certain regions of the country, particularly in the more heavily populated eastern half of the United States, may experience shortfalls during summer peak demand periods. These forecasts considered the utility companies' plans, as of 1989, to meet electricity needs during the period; these plans include such measures as constructing additional generators and conducting demand management programs. Working closely with the nuclear industry, DOE is supporting the development of several reactor technologies to ensure that nuclear power remains a viable electricity supply option. In fiscal year 1990, DOE's Civilian Reactor Development Program was funded at $253 million. DOE is using these funds to support industry-led efforts to develop light water reactors (LWR), advanced liquid-metal reactors (LMR), and modular high-temperature gas-cooled reactors (MHTGR) that are safe, environmentally acceptable, and economically competitive. The utility company officials we spoke with, all of whom were in the Southeast, generally supported DOE's efforts in developing these technologies. However, most of the officials do not plan to purchase nuclear reactors until after 2000 because of the high costs of constructing nuclear reactors and current public opposition to nuclear power

  19. Development and verification of a three-dimensional core model for WWR type reactors and its coupling with the accident code ATHLET. Final report

    International Nuclear Information System (INIS)

    Grundmann, U.; Lucas, D.; Mittag, S.; Rohde, U.

    1995-04-01

    The main goal of the project was the coupling of the 3D core model DYN3D for Russian VVER-type reactors, which has been developed in the RCR, with the thermohydraulic code ATHLET. The coupling has been realized on two basically different ways: - The implementation of only the neutron kinetics model of DYN3D into ATHLET (internal coupling), - the connection of the complete DYN3D core model including neutron kinetics, thermohydraulics and fuel rod model via data interfaces at the core top and bottom (external coupling). For the test of the coupling, comparative calculations between internal and external coupling versions have been carried out for a LOCA and a reactivity transient. Complementary goals of the project were: - The development of a DYN3D version for burn-up calculations, - the verification of DYN3D on benchmark tasks and experimental data on fuel rod behaviour, - a study on the extension of the neutron-physical data base. The project contributed to the development of advanced tools for the safety analysis of VVER-type reactors. Future work is aimed to the verification of the coupled code complex DYN3D-ATHLET. (orig.) [de

  20. Mathematical model use for evaluation of radioactivity spreading in nuclear power plant

    International Nuclear Information System (INIS)

    Kubik, I.; Gladki, Eh.; Yanchik, O.

    1976-01-01

    On the basis of knowledges of radioactive products behaviour and their spreading in nuclear power plant under normal and accident conditions a KOMPLEX program is developed in the FORTRAN 4 language, permitting to calculate the activity in separate parts of the nuclear power plant with WWR type reactor. The COMPLEX program includes the following subprograms: AZ - PRIM - for estimating active products in fuel, coolant, on the surfaces of fuel element cans and the primary circuit. The subprogram permits to estimate the coolant activity at the expense of fission fragments for 4 different leakage mechanisms: due to diffusion, considerable fuel element damage, contamination of fuel element can surface and fuel washout by coolant; KOR - the program for estimating active corrosion products; ACT - the program for estimating the activity of activation products; CONT - the program for estimating the activity in the nuclear power plant premises (protection envelop) and ventilating pipe. The desciption of the above subprograms is given. For testing of the mathematical model applicability and the possibilities of the corresponding programs the checking calculations for operating parameters of nuclear power plant with WWR type reactor were carried out. The calculation results obtained have shown the applicability of the model suggested and the corresponding programes for nuclear power plant under normal operation and accident conditions [ru

  1. Actions for continued safe wet storage of spent nuclear fuel at VVR-S reactor in Bucharest-Magurele

    International Nuclear Information System (INIS)

    Isbasescu, M.; Zorliu, A.; Silviu-laurentiu, B.; Stefan, V. . E-mail address of corresponding author: mirifa@ifin.nipne.ro; Isbasescu, M.)

    2005-01-01

    The Romanian VVR-S research reactor is located 8 kilometers from Bucharest in the town of Magurele and was operated by the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH). The reactor first reached criticality in July 1957 and operated until December 1997 when it was permanently shutdown. The VVR - S reactor of IFIN has two repositories for spent fuel elements: (1) Cooling pool located in the reactor room; (2) Long-term repositories located outside the reactor building - SNFW (spent nuclear fuel warehouse). The major factors believed to influence the pitting of aluminium alloys are conductivity, pH, and bicarbonate, chloride, sulphate and oxygen content. Some of these parameters have been analyzed at SNFW-IFIN-HH. (author)

  2. Detailed magnetic survey at Dahshour archeological sites Southwest Cairo, Egypt

    Science.gov (United States)

    Mekkawi, Mahmoud; Arafa-Hamed, Tarek; Abdellatif, Tareq

    2013-06-01

    Dahshour area has recently shown a great potential of archeological findings. This was remarkable from the latest discovery of the causeway and the mortuary temple of the Pyramid of Amenemhat III using geophysical data. The main objective of the present work is to locate the buried archeological remains in the area of Dahshour, Southwest Cairo using magnetic survey for shallow investigations. Land magnetic data is acquired using proton magnetometer (two sensors) with a sensor separation of 0.8 m; i.e. gradiometer survey. The study area is located nearby the two known pyramids of Dahshour. The field data is processed and analyzed using Oasis Montaj Geosoft™ software. The processed data is presented in order to delineate the hidden artifacts causing the magnetic anomalies. The results indicated a distribution of the buried archeological features within the study area. These archeological features are detected according to the magnetic contrast between the magnetic archeological sources (such as mud bricks, basalt and granite) and the surroundings; mainly sandy soil. The delineated archeological features at Dahshour are probably dated back to the old kingdom having a depth reach up to 3.0 m. Consequently it is highly recommended to carry out excavation to precisely classify them and high light their nature and value.

  3. 76 FR 44964 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S...

    Science.gov (United States)

    2011-07-27

    ... Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting The ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR) will hold a meeting on August 18, 2011, Room T-2B3, 11545 Rockville Pike... the meeting, if possible, so that appropriate arrangements can be made. Thirty-five hard copies of...

  4. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2002-04-01

    SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

  5. ASN’s actions in GEN IV reactors and Sodium Fast Reactors (SFR)

    International Nuclear Information System (INIS)

    Belot, Clotilde

    2013-01-01

    The ASN is involved in 3 actions concerning GEN IV: • Overview of nuclear reactor GEN IV systems; • Specific analysis about transmutation; • Prototype reactor ASTRID (SFR). Furthermore theses actions are in the beginning (no conclusions or results available)

  6. 77 FR 74697 - Meeting of the ACRS, Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting

    Science.gov (United States)

    2012-12-17

    ..., Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting The ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR) will hold a meeting on January 17, 2013, Room T-2B1, 11545 Rockville Pike... be made. Thirty-five hard copies of each presentation or handout should be provided to the DFO thirty...

  7. Prevalence of Bacillus cereus in milk and rice grains collected from great Cairo

    International Nuclear Information System (INIS)

    Abo State, M.A.M.; Youssef, B.M.

    2012-01-01

    Sixty two Samples of heat treated milk, raw rice grains and Cheetos (XO-Snacks) were collected from supermarkets of great Cairo. Seventeen out of 25 milk samples (68%) gave detectable count of B. cereus on MYP medium. These positive samples count was ranging from 1.5 X 10 1 cfu/ml to 11.3X10 2 cfu/ml. Eighteen out of 25 Samples of raw rice grains (72%) gave also detectable count on MYP medium also. The count of positive rice grains was ranging from 2.0X10 1 cfu/g to 11.5X10 3 cfu /ml. However one Sample out of 12 Samples (8%) of Cheetos (Snacks) was positive with count 3.0X10 2 cfu /g. Gamma irradiation reduced the total bacterial count and B. cereus count gradually. Eight kGy reduced total bacterial count and Bacillus cereus count by 3.1 and 2.2 log cycles respectively.

  8. Deterrence and the Future of U.S.-GCC Defense Cooperation: A Strategic Dialogue Event

    Science.gov (United States)

    2015-07-01

    be taken to help incorporate ballistic missile defense systems into the security architecture of Gulf states. Finally, the United States should...American’s copanelist, the Kuwaiti political scientist, added that the GCC has not fully embraced the idea. “It’s an Egyptian -led project,” he said. “Cairo

  9. Local bifurcation analysis in nuclear reactor dynamics by Sotomayor’s theorem

    International Nuclear Information System (INIS)

    Pirayesh, Behnam; Pazirandeh, Ali; Akbari, Monireh

    2016-01-01

    Highlights: • When the feedback reactivity is considered as a nonlinear function some complex behaviors may emerge in the system such as local bifurcation phenomenon. • The qualitative behaviors of a typical nuclear reactor near its equilibrium points have been studied analytically. • Comprehensive analytical bifurcation analyses presented in this paper are transcritical bifurcation, saddle- node bifurcation and pitchfork bifurcation. - Abstract: In this paper, a qualitative approach has been used to explore nuclear reactor behaviors with nonlinear feedback. First, a system of four dimensional ordinary differential equations governing the dynamics of a typical nuclear reactor is introduced. These four state variables are the relative power of the reactor, the relative concentration of delayed neutron precursors, the fuel temperature and the coolant temperature. Then, the qualitative behaviors of the dynamical system near its equilibria have been studied analytically by using local bifurcation theory and Sotomayor’s theorem. The results indicated that despite the uncertainty of the reactivity, we can analyze the qualitative behavior changes of the reactor from the bifurcation point of view. Notably, local bifurcations that were considered in this paper include transcritical bifurcation, saddle-node bifurcation and pitchfork bifurcation. The theoretical analysis showed that these three types of local bifurcations may occur in the four dimensional dynamical system. In addition, to confirm the analytical results the numerical simulations are given.

  10. Floating nuclear heat. And power station 'Pevec' with KLT-40S type reactor plant for remote regions of Russia

    International Nuclear Information System (INIS)

    Veshnyakov, K.B.; Kiryushin, A.I.; Panov, Yu.K.; Polunichev, V.I.

    2000-01-01

    Floating small nuclear power plants power for local energy systems of littoral regions of Russia, located far from central energy system, open a new line in nuclear power development. Designing a floating power unit of a lead nuclear heat and power generating station for port Pevec at the Chuckchee national district is currently nearing completion. Most labor-intensive components are being manufactured. The co-generation NPP Pevec is to be created on the basis of a floating power unit with KLT-40S type reactor plant. KLT-40S reactor plant is based on similar propulsion plants, verified at operation of Russia's nuclear-powered civil ships, evolutionary improved by elimination of 'weak points' revealed during its prototypes operation or on the basis of safety analysis. KLT-40S reactor plant uses the most wide-spread and developed in the world practice PWR-type reactor. KLT-40S meets contemporary national and international requirements imposed to future reactor plants. The NHPS description, its main technical-economic data, environmental safety indices, basic characteristics of KLT-40S reactor plant are presented. Prospects of small NPPs utilization outside Russia, particularly as an energy source for sea water desalination, are considered. (author)

  11. A small research reactor for the 1980's

    International Nuclear Information System (INIS)

    Baglin, C.; Collis-Smith, J.A.; Mitchell, B.; Roskilly, T.

    1978-01-01

    In 1960, GEC together with Imperial College, designed and built the Consort reactor which is still in daily use at the London University Reactor Centre, Silwood Park. In 1977, GEC-REL chose the Consort reactor as a prototype for the development of a modern swimming pool research reactor, designed to meet the needs of countries or organisations starting in the field of Nuclear Technology. This paper outlines some of the topics which arose in the course of this project. (author)

  12. U.S. Department of Energy operational experience with shipments of foreign research reactor spent nuclear fuel

    International Nuclear Information System (INIS)

    Messick, Charles E.; Massey, Charles D.; Mustin, Tracy P.

    1998-01-01

    On May 13, 1996, the U.S. Department of Energy issued a Record of Decision on a Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. The goal of the long-term policy is to recover enriched uranium exported from the United States, while giving foreign research reactor operators sufficient time to develop their own long-term solutions for storage and disposal of spent fuel. The spent fuel accepted by the U.S. DOE under the policy must be out of the research reactors by May 12, 2006 and returned to the United States by May 12, 2009. (author)

  13. Proposal for a strategic management plan for experimental agricultural and academic farm "El Cairo" of Arauca

    Directory of Open Access Journals (Sweden)

    Elías Nieves

    2014-04-01

    Full Text Available This paper presents a design for a strategic management plan for the Experimental Agricultural and Academic Farm: El Cairo of the Universidad Nacional de Colombia, Orinoquía branch. A non-experimental methodological design was used, from which a situational analysis of the farm was generated, which was used as a basis to formulate and design a Strategic Management plan for a five-year period. It was concluded that the current organization and management plan does not meet the mission objectives of research, teaching, and continuing education, suggesting a need for the articulation of the farm with the administrative and academic structure of the university in carrying out the strategic management plan derived from the current research.

  14. In-situ stripping of H{sub 2}S in gasoil hydrodesulphurization - reactor design considerations

    Energy Technology Data Exchange (ETDEWEB)

    Nava, J.A.O.; Krishna, R. [Amsterdam Univ., Dept. of Chemical Engineering, Amsterdam (Netherlands)

    2004-02-01

    In order to meet future diesel specifications the sulphur content of diesel would need to be reduced to below 50 ppm. This requirement would require improved reactor configurations. In this study we examine the benefits of counter-current contacting of gas oil with H{sub 2}, over conventional co-current contacting in a trickle bed hydrodesulphurization (HDS) reactor. In counter-current contacting, we achieve in-situ stripping of H{sub 2}S from the liquid phase; this is beneficial to the HDS kinetics. A comparison simulation study shows that counter-current contacting would require about 20% lower catalyst load than co-current contacting. However, counter-current contacting of gas and liquid phases in conventionally used HDS catalysts, of 1.5 mm sizes, is not possible due to flooding limitations. The catalysts need to be housed in special wire gauze envelopes as in the catalytic bales or KATAPAK-S configurations. A preliminary hardware design of a counter-current HDS reactor using catalytic bales was carried out in order to determine the technical feasibility. Using a realistic sulphur containing feedstock, the target of 50 ppm S content of desulphurized oil could be met in a reactor of reasonable dimensions. The study also underlines the need for accurate modelling of thermal effects during desulphurization. Our study also shows that interphase mass transfer is unlikely to be a limiting factor and there is a need to develop improved reactor configurations allowing for increased catalyst loading, at the expense of gas-liquid interfacial area. (Author)

  15. The U.S. DOE new production reactor/heavy water reactor facility pollution prevention/waste minimization program

    International Nuclear Information System (INIS)

    Kaczmarsky, Myron M.; Tsang, Irving; Stepien, Walter P.

    1992-01-01

    A Pollution Prevention/Waste Minimization Program was established during the early design phase of the U.S. DOE's New Production Reactor/Heavy Water Reactor Facility (NPR/HWRF) to encompass design, construction, operation and decommissioning. The primary emphasis of the program was given to waste elimination, source reduction and/or recycling to minimize the quantity and toxicity of material before it enters the waste stream for treatment or disposal. The paper discusses the regulatory and programmatic background as it applies to the NPR/HWRF and the waste assessment program developed as a phased approach to pollution prevention/waste minimization for the NPR/HWRF. Implementation of the program will be based on various factors including life cycle cost analysis, which will include costs associated with personnel, record keeping, transportation, pollution control equipment, treatment, storage, disposal, liability, compliance and oversight. (author)

  16. Characterization of the Mamluk painting materials in Cairo, Egypt: El-Ashraf Bersbay Madrasa (826 A.H/ 1423 A.D) a case study.

    OpenAIRE

    prof.Atef Brania

    2010-01-01

    The painting materials in the Islamic monuments in Cairo were variable and distinguished. The accurate identification and characterization of painting materials in an art object or in a paint layer is certainly an important step in the history of art, technology and conservation. The main objective of the present paper is to examine and investigate the different painting materials (pigments, gilding, binding media and painting ground) employed in the decorated ceilings of Madrasa of Al-Ashraf...

  17. Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s

    International Nuclear Information System (INIS)

    Wright, A.E.; Dutt, D.S.; Harrison, L.J.

    1990-01-01

    Several series of fast reactor safety tests were performed in TREAT during the 1980s. These focused on the transient behavior of full-length oxide fuels (US reference, UK reference, and US advanced design) and on modern metallic fuels. Most of the tests addressed fuel behavior under transient overpower or loss-of-flow conditions. The test series were the PFR/TREAT tests; the RFT, TS, CDT, and RX series on oxide fuels; and the M series on metallic fuels. These are described in terms of their principal results and relevance to analyses and safety evaluation. 4 refs., 3 tabs

  18. Long-Term, High-Resolution Survey of Atmospheric Aerosols over Egypt with NASA’s MODIS Data

    Directory of Open Access Journals (Sweden)

    Mohammed Shokr

    2017-10-01

    Full Text Available A decadal survey of atmospheric aerosols over Egypt and selected cities and regions is presented using daily aerosol optical depth (AOD data from NASA’s Moderate Resolution Imaging Spectroradiometer (MODIS at 550 nm wavelength onboard the Aqua satellite. We explore the AOD spatio-temporal variations over Egypt during a 12-year record (2003 to 2014 using the MODIS high-resolution (10 km Level 2 data product. Five cities and two geographic regions that feature different landscape and human activities were selected for detailed analysis. For most of the examined areas, AOD is found to be most frequent in the 0.2–0.3 range, and the highest mean AOD was found to be over Cairo, Alexandria, and the Nile Delta region. Severe events are identified based on AOD higher than a selected threshold. Most of these events are engendered by sand and dust storms that originate from the Western Desert during January–April. Spatial analysis indicates that they cover the Nile Delta region, including cities of Cairo and Alexandria, on the same day. Examination of the spatial gradient of AOD along the four cardinal directions originating from the city’s center reveals seasonally dependent gradients in some cases. The gradients have been linked to locations of industrial activity. No trend of AOD has been observed in the studied areas during the study period, though data from Cairo and Asyut reveal a slight linear increase of AOD. Considering Cairo is commonly perceived as a city of poor air quality, the results show that local events are fairly constrained. The study highlights spatial and seasonal distributions of AOD and links them to geographic and climatic conditions across the country.

  19. Neutron activation analysis of airborne inorganic pollutants

    International Nuclear Information System (INIS)

    Oerdoegh, M.; Kalman, L.

    1975-01-01

    The aim of the studies was to determine the radioactive and non-radioactive pollution of the air in the environment of the atomic reactor WWR-S of the Hungarian Academy of Sciences. Accordingly the investigations were carried out by two ways: the samples were analysed partly without previous irradiation and partly by neutron activation analysis. The use of several filter papers was studied and the most suitable filter paper (Whatman No. 41) was chosen for this investigation. The quantitative determination of more than twenty elements has been performed. First the natural activity of the aerosol samples taken periodically was measured and subsequently they have been analysed after irradiation in the atomic reactor for 1 minute, 1 hour, and 50 hours, respectively. A 45 cm 3 Ge/Li detector/ Nuclear Diodes/ was used in connection with a 1024 channel analyzer /type NTA-512B/. The analyses were made nondestructively, and the gamma-spectra were evaluated by computer. (K.A.)

  20. Preliminary assessment of an S.G.H.W. type research reactor

    International Nuclear Information System (INIS)

    Bicevskis, A.; Chapman, A.G.; Hesse, E.W.

    1970-08-01

    A preliminary design study has been made of a research reactor, based on the enriched S.G.H.W.R. concept, to be used for power reactor fuel irradiation, isotope production, basic research, and training in nuclear technology. A reactor physics assessment established a core size which would allow uninterrupted operation for the required irradiation period consistent with low capital and operating costs. A design was selected with 24 channels, a D 2 O calandria diameter of 2.7 m and an overall core height of 4.0 m. The capital cost was estimated as $750,000 for the fuel and $1,600,000 for the moderator, the refuelling cost being $340,000 per annum. A thermal design study showed that the fission heat of 65 MW could be transmitted to pressurised light water at 200 lb/in 2 abs. and rejected to sea water in two conventional U-tube heat exchangers. The basic design is flexible and can be adapted to meet many special requirements. (author)

  1. Genetic characterisation of multidrug-resistant Salmonella enterica serotypes isolated from poultry in Cairo, Egypt

    Directory of Open Access Journals (Sweden)

    Mohammed Abdel-Maksoud

    2015-05-01

    Full Text Available Background: Food-borne diseases pose serious health problems, affecting public health and economic development worldwide. Methods: Salmonella was isolated from samples of chicken parts, skin samples of whole chicken carcasses, raw egg yolks, eggshells and chicken faeces. Resulting isolates were characterised by serogrouping, serotyping, antimicrobial susceptibility testing and detection of extended-spectrum β-lactamase (ESBL production. Antibiotic resistance genes and integrons were identified by polymerase chain reaction (PCR. Results: The detection rates of Salmonella were 60%, 64% and 62% in chicken parts, skin, and faeces, respectively, whereas the egg yolks and eggshells were uniformly negative. Salmonella Kentucky and S. Enteritidis serotypes comprised 43.6% and 2.6% of the isolates, respectively, whilst S. Typhimurium was absent. Variable resistance rates were observed against 16 antibiotics; 97% were resistant to sulfamethoxazole, 96% to nalidixic acid and tetracycline and 76% to ampicillin. Multidrug resistance was detected in 82% (64/78 of the isolates and ESBL production was detected in 8% (6/78. The β-lactamase blaTEM-1 gene was detected in 57.6% and blaSHV-1 in 6.8% of the isolates, whilst the blaOXA gene was absent. The sul1gene was detected in 97.3% and the sul2 gene in 5.3% of the isolates. Sixty-four of the 78 isolates (82% were positive for the integrase gene (int I from class 1 integrons, whilst int II was absent. Conclusion: This study reveals the presence of an alarming number of multidrug-resistant Salmonella isolates in the local poultry markets in Cairo. The high levels of drug resistance suggest an emerging problem that could impact negatively on efforts to prevent and treat poultry and poultry-transmitted human diseases in Egypt.

  2. The regulation on commercial reactors and the management of high-level radioactive wastes in U.S

    International Nuclear Information System (INIS)

    Shimomura, Hidetsugu

    2013-01-01

    This article shows U.S. NRC's substantial and procedural regulations regarding commercial reactors and radioactive wastes. The commercial reactor's regulations are analyzed from an ensuring safety, and the radioactive waste' management is done from a locating a disposal site. (author)

  3. Management of the radioactive waste resulting from the Romanian VVR-S research reactor decommissioning

    International Nuclear Information System (INIS)

    Ene, D.; Cepraga, D.G.

    2002-01-01

    The paper consists in a waste study of the Romanian VVR-S reactor which will be prepared for decommissioning operations after the permanent shutdown (23.12.1997). Calculations were carried out to determine the activity arising from neutron activation of structural materials inside the reactor, considering the design of the facility and its operating rules. To this end, the following method was used: i) Neutron flux distribution within the reactor was calculated using the DORT transport code, based on DLC23 shielding library relating to three cylindrical reference systems of the reactor structure: reactor core, horizontal tube and thermal column; ii) Calculation of the activity of each reactor component at different cooling times was performed by the ANITA2000 code, using the neutron flux, compositional data for each material and the power history of the reactor; iii) Unconditional clearance indexes for all material at various cooling times were calculated using the clearance levels defined in IAEA-TECDOC-855; iv) Total activities and masses by material type, within the waste category and for each decay time were calculated by summation of the data previously classified for each reactor component. The resulting activation inventory and waste masses, falling in IAEA defined waste categories are presented in the paper at periods of 100 days, and 6, 10, 25, and 50 years after reactor the shutdown. For some components of the reactor as: aluminum central vessel, the central iron shielding ring, the time behaviour of both the fin spatial activity distribution and the radionuclide contributions to the total activity are plotted in the paper. (author)

  4. Integral Inherently Safe Light Water Reactor (I2S-LWR)

    International Nuclear Information System (INIS)

    Petrovic, Bojan; Memmott, Matthew; Boy, Guy; Charit, Indrajit; Manera, Annalisa; Downar, Thomas; Lee, John; Muldrow, Lycurgus; Upadhyaya, Belle; Hines, Wesley; Haghighat, Alierza

    2017-01-01

    This final report summarizes results of the multi-year effort performed during the period 2/2013- 12/2016 under the DOE NEUP IRP Project ''Integral Inherently Safe Light Water Reactors (I 2 S-LWR)''. The goal of the project was to develop a concept of a 1 GWe PWR with integral configuration and inherent safety features, at the same time accounting for lessons learned from the Fukushima accident, and keeping in mind the economic viability of the new concept. Essentially (see Figure 1-1) the project aimed to implement attractive safety features, typically found only in SMRs, to a larger power (1 GWe) reactor, to address the preference of some utilities in the US power market for unit power level on the order of 1 GWe.

  5. The CEA research reactors

    International Nuclear Information System (INIS)

    Schwartz, J.P.

    1993-01-01

    Two main research reactors, specifically designed, PEGASE reactor and Laue-Langevin high flux reactor, are presented. The PEGASE reactor was designed at the end of the 50s for the study of the gas cooled reactor fuel element behaviour under irradiation; the HFR reactor, was designed in the late 60s to serve as a high yield and high level neutron source. Historical backgrounds, core and fuel characteristics and design, flux characteristics, etc., are presented. 5 figs

  6. U.S. Department of Energy Program of International Technical Cooperation for Research Reactor Utilization

    International Nuclear Information System (INIS)

    Chong, D.; Manning, M.; Ellis, R.; Apt, K.; Flaim, S.; Sylvester, K.

    2004-01-01

    The U.S. Department of Energy, National Nuclear Security Administration (DOE/NNSA) has initiated collaborations with the national nuclear authorities of Egypt, Peru, and Romania for the purpose of advancing the commercial potential and utilization of their respective research reactors. Under its Office of International Safeguards ''Sister Laboratory'' program, DOE/NNSA has undertaken numerous technical collaborations over the past decade intended to promote peaceful applications of nuclear technology. Among these has been technical assistance in research reactor applications, such as neutron activation analysis, nuclear analysis, reactor physics, and medical radioisotope production. The current collaborations are intended to provide the subject countries with a methodology for greater commercialization of research reactor products and services. Our primary goal is the transfer of knowledge, both in administrative and technical issues, needed for the establishment of an effective business plan and utilization strategy for the continued operation of the countries' research reactors. Technical consultation, cooperation, and the information transfer provided are related to: identification, evaluation, and assessment of current research reactor capabilities for products and services; identification of opportunities for technical upgrades for new or expanded products and services; advice and consultation on research reactor upgrades and technical modifications; characterization of markets for reactor products and services; identification of competition and estimation of potential for market penetration; integration of technical constraints; estimation of cash flow streams; and case studies

  7. Persistent semi-metal-like nature of epitaxial perovskite CaIrO3 thin films

    International Nuclear Information System (INIS)

    Biswas, Abhijit; Jeong, Yoon Hee

    2015-01-01

    Strong spin-orbit coupled 5d transition metal based ABO 3 oxides, especially iridates, allow tuning parameters in the phase diagram and may demonstrate important functionalities, for example, by means of strain effects and symmetry-breaking, because of the interplay between the Coulomb interactions and strong spin-orbit coupling. Here, we have epitaxially stabilized high quality thin films of perovskite (Pv) CaIrO 3 . Film on the best lattice-matched substrate shows semi-metal-like characteristics. Intriguingly, imposing tensile or compressive strain on the film by altering the underlying lattice-mismatched substrates still maintains semi-metallicity with minute modification of the effective correlation as tensile (compressive) strain results in tiny increases (decreases) of the electronic bandwidth. In addition, magnetoresistance remains positive with a quadratic field dependence. This persistent semi-metal-like nature of Pv-CaIrO 3 thin films with minute changes in the effective correlation by strain may provide new wisdom into strong spin-orbit coupled 5d based oxide physics

  8. V.S.O.P. (99/09) computer code system for reactor physics and fuel cycle simulation. Version 2009

    Energy Technology Data Exchange (ETDEWEB)

    Ruetten, H.J.; Haas, K.A.; Brockmann, H.; Ohlig, U.; Pohl, C.; Scherer, W.

    2010-07-15

    V.S.O.P. (99/ 09) represents the further development of V.S.O.P. (99/ 05). Compared to its precursor, the code system has been improved again in many details. The main motivation for this new code version was to update the basic nuclear libraries used by the code system. Thus, all cross section libraries involved in the code have now been based on ENDF/B-VII. V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. It implies the setup of the reactor and of the fuel element, processing of cross sections, neutron spectrum evaluation, neutron diffusion calculation in two or three dimensions, fuel burnup, fuel shuffling, reactor control, thermal hydraulics and fuel cycle costs. The thermal hydraulics part (steady state and time-dependent) is restricted to gas-cooled reactors and to two spatial dimensions. The code can simulate the reactor operation from the initial core towards the equilibrium core. This latest code version was developed and tested under the WINDOWS-XP - operating system. (orig.)

  9. V.S.O.P. (99/09) computer code system for reactor physics and fuel cycle simulation. Version 2009

    International Nuclear Information System (INIS)

    Ruetten, H.J.; Haas, K.A.; Brockmann, H.; Ohlig, U.; Pohl, C.; Scherer, W.

    2010-07-01

    V.S.O.P. (99/ 09) represents the further development of V.S.O.P. (99/ 05). Compared to its precursor, the code system has been improved again in many details. The main motivation for this new code version was to update the basic nuclear libraries used by the code system. Thus, all cross section libraries involved in the code have now been based on ENDF/B-VII. V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. It implies the setup of the reactor and of the fuel element, processing of cross sections, neutron spectrum evaluation, neutron diffusion calculation in two or three dimensions, fuel burnup, fuel shuffling, reactor control, thermal hydraulics and fuel cycle costs. The thermal hydraulics part (steady state and time-dependent) is restricted to gas-cooled reactors and to two spatial dimensions. The code can simulate the reactor operation from the initial core towards the equilibrium core. This latest code version was developed and tested under the WINDOWS-XP - operating system. (orig.)

  10. Passive Decay Heat Removal System Options for S-CO2 Cooled Micro Modular Reactor

    International Nuclear Information System (INIS)

    Moon, Jangsik; Jeong, Yong Hoon; Lee, Jeong Ik

    2014-01-01

    To achieve modularization of whole reactor system, Micro Modular Reactor (MMR) which has been being developed in KAIST took S-CO 2 Brayton power cycle. The S-CO 2 power cycle is suitable for SMR due to high cycle efficiency, simple layout, small turbine and small heat exchanger. These characteristics of S-CO 2 power cycle enable modular reactor system and make reduced system size. The reduced size and modular system motived MMR to have mobility by large trailer. Due to minimized on-site construction by modular system, MMR can be deployed in any electricity demand, even in isolated area. To achieve the objective, fully passive safety systems of MMR were designed to have high reliability when any offsite power is unavailable. In this research, the basic concept about MMR and Passive Decay Heat Removal (PDHR) system options for MMR are presented. LOCA, LOFA, LOHS and SBO are considered as DBAs of MMR. To cope with the DBAs, passive decay heat removal system is designed. Water cooled PDHR system shows simple layout, but has CCF with reactor systems and cannot cover all DBAs. On the other hand, air cooled PDHR system with two-phase closed thermosyphon shows high reliability due to minimized CCF and is able to cope with all DBAs. Therefore, the PDHR system of MMR will follows the air-cooled PDHR system and the air cooled system will be explored

  11. Practical Study on Treatment of Selected Decorated Tapestry in Applied Art Museum, Cairo

    Directory of Open Access Journals (Sweden)

    Neven Kamal FAHIM

    2013-12-01

    Full Text Available The paper presents the method of treatment of tapestry textile, that considers the most common technique used in decoration of textile since the new kingdom until now, it is called Kabaty. The paper deals with selected piece of museum of Applied Art Faculty in Cairo. Treatment procedure was performed by several stages; firstly, Dating by comparing the decoration technique, the type of material and the decorative motifs existed in the object with another one known its date. Then samples taken from object were examined by optical microscope, scanning electron microscope to identify type of fibers and surface morphology .x-ray analysis was performed to identify mordant and dust. FTIR analysis to identify dyes in dyed samples. Then, the paper deal with the treatment of tapestry pieces by testing sensitive of fiber to water, mechanical cleaning and chemical cleaning to remove stain, washing stage using distilled water, and finally consolidation the object by fixed on support of natural linen which was stretched on wooden frame treated by anti-fungal substance.

  12. Cairo conference to link population and sustainable development.

    Science.gov (United States)

    1994-09-01

    Couples who want to limit the size of their families but whom family planning services elude are a key factor in the persistence of high rates of fertility and rapid population growth in some countries of the Asian and Pacific region (ESCAP). High fertility and rapid growth are linked to high rates of maternal and child mortality, poverty, and increasing pressure on the environment. These issues will be considered at the International Conference on Population and Development at Cairo from 5 to 13 September, 1994. The Conference objectives entail the promotion of more effective national programs to meet individual needs of women, and to bring population into balance with available resources. The Conference is expected to adopt a program of action covering the period 1995-2015. A preparatory meeting, the Fourth Asian and Pacific Population Conference, adopted the Bali Declaration on Population and Development as a blueprint for ESCAP region countries. Unprecedented growth in human numbers, widespread poverty, social and economic in equality and wasteful consumption are accelerating the depletion of resources and environmental degradation. Rural-to-urban migration will also be major concerns at the Conference. Real poverty and unemployment are the leading causes of urbanization. Recent United Nations data show that by 2005 half the world's population will be urban. Development policies affecting the rural work-force need to emphasize gender equity and access to land tenure and credit. Economic growth and improvement in the quality of life have been fastest in those areas where the status of women is highest, therefore population policies will succeed only if women are equal to men in making and directing policy. The draft Program of Action would commit the world community to goals in education, especially for girls; reduction of infant, child and maternal mortality; and universal access to family planning and reproductive health services.

  13. Safety evaluation report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission for U.S. Energy Research and Development Administration Light Water Breeder Reactor. Special project No. 561

    International Nuclear Information System (INIS)

    1976-07-01

    The Safety Evaluation Report is presented for the Light Water Breeder Reactor (LWBR). The LWBR core is to be installed in the Shippingport reactor at the Shippingport Atomic Power Station. The Safety Evaluation Report is the result of an NRC staff review of the LWBR Safety Analysis Report submitted by the Division of Naval Reactors, U. S. Energy Research and Development Administration. As a result of its review, the NRC staff has recommended that: (1) a diverse trip signal, such as containment high pressure, be included in a 2-out-of-3 logic for initiation of safety injection; (2) power be locked out from the pressurizer surge isolation valve during normal operation; and (3) a chlorine monitor be installed in the main control room

  14. Experimental study on Response Parameters of Ni-rich NiTi Shape Memory Alloy during Wire Electric Discharge Machining

    Science.gov (United States)

    Bisaria, Himanshu; Shandilya, Pragya

    2018-03-01

    Nowadays NiTi SMAs are gaining more prominence due to their unique properties such as superelasticity, shape memory effect, high fatigue strength and many other enriched physical and mechanical properties. The current studies explore the effect of machining parameters namely, peak current (Ip), pulse off time (TOFF), and pulse on time (TON) on wire wear ratio (WWR), and dimensional deviation (DD) in WEDM. It was found that high discharge energy was mainly ascribed to high WWR and DD. The WWR and DD increased with the increase in pulse on time and peak current whereas high pulse off time was favourable for low WWR and DD.

  15. U.S. Research Program to Support Advanced Reactors and Fuel Cycle Options

    International Nuclear Information System (INIS)

    Lyons, Peter

    2013-01-01

    • In recognition of possible future needs, the U.S. will perform R&D on advanced reactor and fuel cycle technologies that could dramatically improve nuclear energy safety and performance; • Multifaceted approach to support R&D: - National labs; - Universities; - Industry; - International partners

  16. V.S.O.P.-computer code system for reactor physics and fuel cycle simulation

    International Nuclear Information System (INIS)

    Teuchert, E.; Hansen, U.; Haas, K.A.

    1980-03-01

    V.S.O.P. (Very Superior Old Programs) is a system of codes linked together for the simulation of reactor life histories. It comprises neutron cross section libraries and processing routines, repeated neutron spectrum evaluation, 2-D diffusion calculation based on neutron flux synthesis with depletion and shutdown features, incore and out-of-pile fuel management, fuel cycle cost analysis, and thermal hydraulics (at present restricted to Pebble Bed HTRs). Various techniques have been employed to accelerate the iterative processes and to optimize the internal data transfer. A limitation of the storage requirement to 360 K-bites is achieved by an overlay structure. The code system has been used extensively for comparison studies of reactors, their fuel cycles, and related detailed features. Beside its use in research and development work for the high temperature reactor the system has been applied successfully to LWR and Heavy Water Reactors. (orig.) [de

  17. Contribution of geophysical studies on detection of the Petrified Frost Qattamiya, Cairo

    Directory of Open Access Journals (Sweden)

    Sultan Awad Sultan Araffa

    2017-03-01

    Full Text Available Different geophysical tools such as resistivity, seismic refraction, and magnetic survey have been applied to delineate the subsurface stratigraphy and structural elements, which controlled the distribution and origin of the Petrified wood in Qattamiya, Cairo, Egypt. Land magnetic survey was carried out in the study area through two stages, the first stage includes all area by measuring 11,674 stations and the second stage was carried out in the detailed area that was located at the southeastern part of the all area including 9441 stations. All measurements have been corrected for diurnal variation and reduced to the north magnetic pole. The results of magnetic interpretation indicated that the area dissected by different structural elements trend toward NE–SW, NW–SE, N–S and E–W directions. Twenty-eight samples have been collected from the detailed area to analyze for magnetic susceptibility values. Four electrical resistivity tomography (ERT profiles were measured by using dipole–dipole configuration to estimate the vertical and lateral variation of the subsurface sequence. Results of quantitative interpretation of the ERT data indicate that the subsurface sequence consists of different geoelectric units; the first unit is characterized by high resistivity values upto 1000 ohm m corresponding to sand, gravel and Petrified wood at the surface and extends to a depth of a few meters. The second geoelectric unit is corresponding to sandy clay which exhibits moderate resistivity (few hundred ohm m values with thickness ranging from 6 to10 m. The third geoelectric unit is characterized by very low resistivity corresponding to clay of depth ranging from 10 to 30 m overlaying the fourth unit which reached to a depth ranging from 30 to 56 m and characterized by very high resistivity (8000 ohm m corresponding to limestone. Three shallow seismic refraction spreads of geophone spacing 7.5 m were measured to investigate the subsurface

  18. Reactor coolant pump seal issues and their applicability to new reactor designs

    International Nuclear Information System (INIS)

    Ruger, C.J.; Higgins, J.C.

    1993-01-01

    Reactor Coolant Pumps (RCPs) of various types are used to circulate the primary coolant through the reactor in most reactor designs. RCPs generally contain mechanical seals to limit the leakage of pressurized reactor coolant along the pump drive shaft into the containment. The relatively large number of RCP seal and seal auxiliary system failures experienced at U.S. operating plants during the 1970's and early 1980's raised concerns from the U.S. Nuclear Regulatory Commission (NRC) that gross failures may lead to reactor core uncovery and subsequent core damage. Some seal failure events resulted in a loss of primary coolant to the containment at flow rates greater than the normal makeup capacity of Pressurized Water Reactor (PWR) plants. This is an example of RCP seal failures resulting in a small Loss of Coolant Accident (LOCA). This paper discusses observed and potential causes of RCP seal failure and the recommendations for limiting the likelihood of a seal induced small LOCA. Issues arising out of the research supporting these recommendations and subsequent public comments by the utility industry on them, serve as lessons learned, which are applicable to the design of new reactor plants

  19. Nuclear non-proliferation: the U.S. obligation to accept spent fuel from foreign research reactors

    International Nuclear Information System (INIS)

    Shapar, Howard K.; Egan, Joseph R.

    1995-01-01

    The U.S. Department of Energy (DOE) had a 35-year program for the sale and receipt (for reprocessing) of high-enriched research reactor fuel for foreign research reactors, executed pursuant to bilateral agreements with nuclear trading partners. In 1988, DOE abruptly let this program lapse, citing environmental obstacles. DOE promised to renew the program upon completion of an environmental review which was to take approximately six months. After three and a half years, an environmental assessment was finally produced.Over a year and half elapsed since publication of the assessment before DOE finally took action to renew the program. The paper sets forth the nuclear non-proliferation and related foreign policy considerations which support renewal of the program. It also summarized the contractual and other commitments made to foreign research reactors and foreign governments and aspects of U.S. environmental law as they apply to continuation of the program. (author)

  20. La conferencia de El Cairo y la afirmación de los derechos sexuales y reproductivos, como base para la salud sexual y reproductiva

    Directory of Open Access Journals (Sweden)

    Susana Galdos Silva

    2013-09-01

    Full Text Available El artículo se enfoca en la Conferencia Internacional sobre Población y Desarrollo de El Cairo, llevada a cabo en Egipto en 1994, en la cual se trataron temas referidos a derechos sexuales y reproductivos, a las acciones para mejorar la situación de las niñas, el estatus de la mujer, la situación de los adolescentes y la igualdad de género, como componentes básicos para mejorar la salud sexual y reproductiva de la población. Las recomendaciones producto de esta conferencia conforman el programa de acción. En el presente documento se desarrollan, además, algunos temas que durante la conferencia generaron largas discusiones para llegar a un consenso. Resume el seguimiento al programa de acción en los años posteriores y se detiene en el informe del gobierno peruano y la sociedad civil hacia los veinte años de la conferencia.

  1. Lieutenant General Patton’s Seventh Army in Sicily 1943: The Maturation of an American Operational Artist

    Science.gov (United States)

    2014-05-22

    locations included Force 141 at Algiers, Western TF HQ (U.S.) at Rabat, Morocco, Eastern TF HQ (British) at Cairo, Egypt , as well as the HQs for the 45th...and Staff College, 1947. Patton, George S. War As I Knew It. 1947. Reprint, New York: Pyramid , 1966. Province, Charles M., ed. Military Essays

  2. Reactor Physics

    Energy Technology Data Exchange (ETDEWEB)

    Ait Abderrahim, A

    2001-04-01

    The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

  3. Dry reloading and packaging of spent fuel at TRIGA MARK I reactor of Medical University Hanover (MHH), Germany

    International Nuclear Information System (INIS)

    Haferkamp, D.

    2008-01-01

    Between 1994 and 1998 the equipment for dry reloading of a research reactor was developed by Noell, which was funded by the German Federal Government and State of Saxonia. The task of this development programme was the design and delivery of an equipment able to load the spent fuel into the shipping casks in a dry mode for research reactors, where wet loading inside the storage pool is impossible. ALARA and infrastructure conditions had to be taken into consideration. Most of the research reactors of TRIGA MARK I type or WWR-SM have operating modes for handling of spent fuel inside the pond or for transfer of spent fuel from pond to dry/wet storage pools. On the other hand, most of them cannot handle heavy weighted shipping casks inside the reactor building because of the crane capacity, or inside water pool because of dimensions and weight of shipping casks. A typical licensed normal operating procedure for spent fuel in research reactors (TRIGA MARK I) is shown. Dry unloading procedure is described. Additionally to the normal operating procedures at the MHH research reactor the following steps were necessary: - dry packaging of spent fuel elements into the loading units (six packs) in order to minimise the transfer and loading steps between the pool and shipping cask; - transfer of spent fuel loading units from dry storage pool to the shipping cask (outside the reactor building) in a shielded transfer cask; - dry reloading of loading units, into the shipping casks outside the reactor building. The Dry Reloading Equipment implies the following 5 items: 1. loading units (six packs), which includes: - capacity up to six spent fuel elements; - criticality safe placement of spent fuel elements; - handling of several spent fuel elements in an aluminium loading unit. 2. Special Transfer Cask, which includes: - shielded housing with locks; - gripper inside housing; - hoist outside housing; - computer aided operation mode for loading and unloading. 3. Transfer Vehicle

  4. Safety aspects of the FMPP (Fuel Manufacturing Pilot Plant) setup constructed by INVAP in the Arabic Republic of Egypt

    International Nuclear Information System (INIS)

    Cinat, Enrique; Boero, Norma L.

    1999-01-01

    The FMPP is a fuel plates manufacturing plant for test reactors. This facility was designed, constructed in El Cairo and turned-key handled by INVAP SE to the Arabian Republic of Egypt. In this project, CNEA participated in the transference of technology, elaboration of documents, training of Egyptian personnel and technical services during the setup of the facility in El Cairo. These tasks were undertaken by UPMP (Uranium Powder Manufacturing Plant) and ECRI (Research Reactors Fuel Elements Plant) personnel. Both plants in CNEA served as a FMPP design basis. During the setup of the facility a fuel element with natural uranium was firstly manufactured and then another one using uranium with 20% enrichment. In this paper the responses of the system regarding safety, after finishing the first two stages of manufacturing, are analyzed and evaluated. (author)

  5. Safety aspects of the FMPP (Fuel Manufacturing Pilot Plant) setup constructed by INVAP in the Arabic Republic of Egypt; Aspectos de seguridad en la puesta en marcha de la FMPP (Fuel Manufacturing Pilot Plant) construida por INVAP en la Republica Arabe de Egipto

    Energy Technology Data Exchange (ETDEWEB)

    Cinat, Enrique; Boero, Norma L [Comision Nacional de Energia Atomica, General San Martin (Argentina). Dept. de Combustibles Nucleares

    1999-07-01

    The FMPP is a fuel plates manufacturing plant for test reactors. This facility was designed, constructed in El Cairo and turned-key handled by INVAP SE to the Arabian Republic of Egypt. In this project, CNEA participated in the transference of technology, elaboration of documents, training of Egyptian personnel and technical services during the setup of the facility in El Cairo. These tasks were undertaken by UPMP (Uranium Powder Manufacturing Plant) and ECRI (Research Reactors Fuel Elements Plant) personnel. Both plants in CNEA served as a FMPP design basis. During the setup of the facility a fuel element with natural uranium was firstly manufactured and then another one using uranium with 20% enrichment. In this paper the responses of the system regarding safety, after finishing the first two stages of manufacturing, are analyzed and evaluated. (author)

  6. Model-based analysis of an outbreak of bubonic plague in Cairo in 1801.

    Science.gov (United States)

    Didelot, Xavier; Whittles, Lilith K; Hall, Ian

    2017-06-01

    Bubonic plague has caused three deadly pandemics in human history: from the mid-sixth to mid-eighth century, from the mid-fourteenth to the mid-eighteenth century and from the end of the nineteenth until the mid-twentieth century. Between the second and the third pandemics, plague was causing sporadic outbreaks in only a few countries in the Middle East, including Egypt. Little is known about this historical phase of plague, even though it represents the temporal, geographical and phylogenetic transition between the second and third pandemics. Here we analysed in detail an outbreak of plague that took place in Cairo in 1801, and for which epidemiological data are uniquely available thanks to the presence of medical officers accompanying the Napoleonic expedition into Egypt at that time. We propose a new stochastic model describing how bubonic plague outbreaks unfold in both rat and human populations, and perform Bayesian inference under this model using a particle Markov chain Monte Carlo. Rat carcasses were estimated to be infectious for approximately 4 days after death, which is in good agreement with local observations on the survival of infectious rat fleas. The estimated transmission rate between rats implies a basic reproduction number R 0 of approximately 3, causing the collapse of the rat population in approximately 100 days. Simultaneously, the force of infection exerted by each infected rat carcass onto the human population increases progressively by more than an order of magnitude. We also considered human-to-human transmission via pneumonic plague or human specific vectors, but found this route to account for only a small fraction of cases and to be significantly below the threshold required to sustain an outbreak. © 2017 The Author(s).

  7. Liquefaction analysis of alluvial soil deposits in Bedsa south west of Cairo

    Directory of Open Access Journals (Sweden)

    Kamal Mohamed Hafez Ismail Ibrahim

    2014-09-01

    Full Text Available Bedsa is one of the districts in Dahshour that lays south west of Cairo and suffered from liquefaction during October 1992 earthquake, Egypt. The soil profile consists of alluvial river Nile deposits mainly sandy mud with low plasticity; the ground water is shallow. The earthquake hypocenter was 18 km far away with local magnitude 5.8; the fault length was 13.8 km, as recorded by the Egyptian national seismological network (ENSN at Helwan. The analysis used the empirical method introduced by the national center for earthquake engineering research (NCEER based on field standard penetration of soil. It is found that the studied area can liquefy since there are saturated loose sandy silt layers at depth ranges from 7 to 14 m. The settlement is about 26 cm. The probability of liquefaction ranges between 40% and 100%. The presence of impermeable surface from medium cohesive silty clay acts as a plug resisting and trapping the upward flow of water during liquefaction, so fountain and spouts at weak points occurs. It is wise to use point bearing piles with foundation level deeper than 14 m beyond the liquefiable depth away from ground slopes, otherwise liquefaction improving techniques have to be applied in the area.

  8. Automation drying unit molybdenum-zirconium gel radioisotope production technetium-99M for nuclear medicine

    International Nuclear Information System (INIS)

    Chakrova, Y.; Khromushin, I.; Medvedeva, Z.; Fettsov, I.

    2014-01-01

    Full text : Since 2001 the Institute of Nuclear Physics of the Republic of Kazakhstan has began production of radiopharmaceutical based on technetium-99m from irradiated reactor WWR-K of natural molybdenum, which allows to obtain a solution of technetium-99m of the required quality and high volume activity. In 2013 an automated system is started, which is unique and urgent task is to develop algorithms and software in Python, as well as the manufacture of certain elements of technological systems for automated production

  9. The concept of the sodium cooled small fast reactor 4S and the analyses of the loss of flow events

    International Nuclear Information System (INIS)

    Nishi, Yoshihisa; Ueda, Nobuyuki; Koga, Tomonari; Matsumiya, Hisato

    2007-01-01

    CRIEPI has been developing the 4S reactor (Super Safe, Small and Simple reactor) for application in dispersed energy supply and multipurpose use, in conjunction with Toshiba Corporation. The 4S is sodium cooled fast reactor and their electrical output has two options of 10MWe and 50MWe. In this paper, 10MWe 4S (4S-10M) was proposed. 4S-10M has some unique features. It employs a burn-up control system with annular reflector in place of the control rod that requires the frequent maintenance service. The core life time of the 4S-10M is 30 years and the fuel transport is not required during core life time. All temperature feedback coefficients are negative during core life time. In the latest design for 4S-10M, a pool and tall type reactor design was selected to reduce the construction cost. Two types of decay heat removal system (Reactor Vessel Auxiliary Cooling System; RVACS, Intermediate Reactor Auxiliary Cooling System; IRACS) using natural convection power were adopted. It is necessary to confirm that these two heat removal system can operate appropriately. The transition analyses were executed by the CERES code to evaluate the design feasibility and the thermal hydraulic characteristics of the 4S-10M. CERES is a multi-dimensional plant dynamics simulation code for liquid metal reactors developed by the CRIEPI. CERES can perform simulations ranging from forced circulation (full/partial power operation) to natural circulation. Components (pumps, IHXs, SGs, pipings, etc.) of the reactor are modeled as one-dimensional. Multi-dimensional plena are connected to such components. Two loss-of-flow accident sequences are considered. In the first case, it is assumed that the primary and the secondary pump were stopped by the total station black out. The reactor shut down system was assumed to be success. This sequence is referred to as the protected loss-of-flow accident (PLOF). In the second case, it is assumed that the reactor shut down systems fail to operate and the

  10. Computational and Experimental Investigations of the Coolant Flow in the Cassette Fissile Core of a KLT-40S Reactor

    Science.gov (United States)

    Dmitriev, S. M.; Varentsov, A. V.; Dobrov, A. A.; Doronkov, D. V.; Pronin, A. N.; Sorokin, V. D.; Khrobostov, A. E.

    2017-07-01

    Results of experimental investigations of the local hydrodynamic and mass-exchange characteristics of a coolant flowing through the cells in the characteristic zones of a fuel assembly of a KLT-40S reactor plant downstream of a plate-type spacer grid by the method of diffusion of a gas tracer in the coolant flow with measurement of its velocity by a five-channel pneumometric probe are presented. An analysis of the concentration distribution of the tracer in the coolant flow downstream of a plate-type spacer grid in the fuel assembly of the KLT-40S reactor plant and its velocity field made it possible to obtain a detailed pattern of this flow and to determine its main mechanisms and features. Results of measurement of the hydraulic-resistance coefficient of a plate-type spacer grid depending on the Reynolds number are presented. On the basis of the experimental data obtained, recommendations for improvement of the method of calculating the flow rate of a coolant in the cells of the fissile core of a KLT-40S reactor were developed. The results of investigations of the local hydrodynamic and mass-exchange characteristics of the coolant flow in the fuel assembly of the KLT-40S reactor plant were accepted for estimating the thermal and technical reliability of the fissile cores of KLT-40S reactors and were included in the database for verification of computational hydrodynamics programs (CFD codes).

  11. Violence, abuse, alcohol and drug use, and sexual behaviors in street children of Greater Cairo and Alexandria, Egypt.

    Science.gov (United States)

    Nada, Khaled H; Suliman, El Daw A

    2010-07-01

    To measure the prevalence of HIV/AIDS risk behaviors and related factors in a large, probability-based sample of boys and girls aged 12-17 years living on the streets of Egypt's largest urban centers of Greater Cairo and Alexandria. Time-location sampling (TLS) was used to recruit a cross-sectional sample of street children. Procedures entailed using key informants and field observation to create a sampling frame of locations at predetermined time intervals of the day, where street children congregate in the two cities, selecting a random sample of time-locations from the complete list, and intercepting children in the selected time-locations to assess eligibility and conduct interviews. Interviews gathered basic demographic information, life events on the street (including violence, abuse, forced sex), sexual and drug use behaviors, and HIV/AIDS knowledge. A total of 857 street children were enrolled in the two cities, with an age, sex, and time-location composition matching the sampling frame. The majority of these children had faced harassment or abuse (93%) typically by police and other street children, had used drugs (62%), and, among the older adolescents, were sexually active (67%). Among the sexually active 15-17-year-olds, most reported multiple partners (54%) and never using condoms (52%). Most girls (53% in Greater Cairo and 90% in Alexandria) had experienced sexual abuse. The majority of street children experienced more than one of these risks. Overlaps with populations at highest risk for HIV were substantial, namely men who have sex with men, commercial sex workers, and injection drug users. Our study using a randomized TLS approach produced a rigorous, diverse, probability-based sample of street children and documented very high levels of multiple concurrent risks. Our findings strongly advocate for multiple services including those addressing HIV and STI prevention and care, substance use, shelters, and sensitization of authorities to the plight of

  12. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-01

    Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T.

  13. Nuclear reactors. Introduction

    International Nuclear Information System (INIS)

    Boiron, P.

    1997-01-01

    This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

  14. Progress in the U.S. department of energy sponsored in-depth safety assessments of VVER and RBMK reactors

    International Nuclear Information System (INIS)

    Binder, J.L.; Petri, M.C.; Pasedag, W.F.

    2001-01-01

    Since the disastrous accident at Chernobyl Nuclear Power Plant Unit 4 in 1986, there has been international recognition of the safety concerns posed by the operation of 67 Soviet-designed commercial nuclear reactors. These reactors are operated in eight countries from the former Soviet Union and its former satellite states in Central and Eastern Europe. The majority of these plants are in the Russian Federation (30 units) and Ukraine (14 units). New plants are in various stages of construction. U.S. support to improve the safety of Soviet-designed reactors over the past decade has been intended to enhance operational safety, provide for risk-reduction measures, and enhance regulatory capability. The U.S. approach to improving the safety of Soviet-designed reactors has matured into a large multi-year program known as the Soviet-Designed Reactor Safety Program that is managed by the U.S. Department of Energy (US DOE). The mission of the program is to implement a self-sustaining nuclear safety improvement program that would lead to internationally accepted safety practices at the plants. Those practices would create a safety culture that would be reflected in the operation, regulation, and professional attitudes of the designers, operators, and regulators of the nuclear facilities. A key component of this larger program has been the Plant Safety Evaluation Program, which supports in-depth safety assessments of VVER and RBMK plants. (author)

  15. Preliminary S-CO_2 Compressor Design for Micro Modular Reactor

    International Nuclear Information System (INIS)

    Lee, Jekyoung; Cho, Seong Kuk; Kim, Seong Gu; Lee, Jeong Ik

    2016-01-01

    Due to economic benefit of S-CO_2 Brayton cycle which is came from high efficiency and compactness, active research is currently conducted by various research groups and various approaches are suggested to take benefits of S-CO_2 Brayton cycle. KAIST research team also has been working on advanced concept for application of S-CO_2 Brayton cycle to nuclear system and Micro Modular Reactor (MMR) concept was suggested. The preliminary compressor design of S-CO_2 compressor for MMR system was carried out to observe feasibility of compressor design. Preliminary S-CO_2 compressor design for MMR system was successfully conducted and some issues are discovered from the design study. From the previous work done by Cho, conceptual design for MMR system was provided. Thus, further preliminary design should be carried out to obtain feasible S-CO_2 compressor design for MMR system. KAIST_TMD which is turbomachinery in-house code for real gases including S-CO_2 is continuously updated and currently it has 3D geometry construction and design optimization capability

  16. Status and program of development of the fast breeder reactor system in the U.S

    International Nuclear Information System (INIS)

    Roberts, R.W.

    1977-01-01

    The U.S. Energy Research and Development Administration's highest priority breeder concept is the Liquid Metal Fast Breeder Reactor (LMFBR). Its objective is the development of a broad technological and engineering base with extensive utility and industrial involvement which will establish a timely capability for a competitive and commercial breeder industry. In addition to technological development, an integral part of the LMFBR program is the transfer of LMFBR technology to the nuclear industry and the parallel development of utility capability. An important indicator of the effectiveness of this program is the successful construction and operation of a number of LMFBR experimental and test reactors and associated non-nuclear test facilities such as those located at Santa Susana, California, the Argonne (III). National Laboratory and the Hanford Engineering Development Laboratory at Richland, Washington. A principal element of the U.S. fast breeder reactor program is the Fast Flux Test Facility (FFTF). The largest test reactor facility in the world, the FFTF will focus on the testing of fuels and material. The FFTF, being built at the Hanford Engineering Development Laboratory, is scheduled for completion in the late 1970's. The next step toward timely commercial breeder capability is to implement a program for a large-scale demonstration of this concept. A 380 megawatt electrical demonstration plant - designated the Clinch River Breeder Reactor Plant (CRBRP) - will be constructed and operated near Oak Ridge, Tennessee, under a cooperative arrangement of industrial contractors, utilities, and the Government. The completion date is 1983. The estimated cost of the CRBRP project is 1.95 billion dollars. This includes the cost of design, construction, related research and development, and five years of operation - the full timespan from the project's beginning in 1972 through completion. The Nation's principal electric utilities have strongly endorsed the

  17. Selection of NPP for Kazakhstan

    International Nuclear Information System (INIS)

    Zhotabaev, Zh.R.

    2003-01-01

    Commercial NPP for Kazakhstan should to meet to several main requirements: 1). Safety operation (accident probability not more than 10 -6 1/p. year). 2). High efficiency > 40 %. 3). Possibility of use for high-temperature chemistry and hydrogen production. 4). Possibility for manufacturing of considerable part of equipment in Kazakhstan. 5). Possibility for fuel production and reprocessing in Kazakhstan. 6). Independence from existence of large water-supply sources. Comparative analysis of several NPP with different reactors (WWR-1000, Candu, BREST, VG-400; graphite molten salt reactor) shows that NPP with the graphite molten salt reactor meets to all above requirements, but hydrogen production it is possible by more complete 4-stage technology, since coolant temperature is 800 Deg. C. The principle advantage is possibility of manufacturing of main equipment and fuel in Kazakhstan that reduce the cost of NPP construction and operation

  18. Formal and informal Patronage among Jews in the Islamic East: evidence from the Cairo Geniza

    Directory of Open Access Journals (Sweden)

    Rustow, Marina

    2008-12-01

    Full Text Available This paper investigates the political culture of the Islamic East under Fatimid and Buwayhid rule (tenth-twelfth centuries via relationships between patrons, clients, protégés, and partners. The main body of evidence I utilize are letters and petitions from the Cairo Geniza that employ the same specialized vocabulary of patron-client relationships one finds in Arabic histories of the period: idioms referring to the exchange of benefit, reciprocal service, protection, oversight, patronage, and loyalty. The Geniza letters, written without regard for posterity, suggest that these idioms were used well beyond the courts and were understood and deployed by men and women, the literate and illiterate, the important and the inconsequential. Yet the use of certain terms in Judaeo-Arabic also differs from their use in Arabic: some reflect devaluation over time, while others hardened into formulaic phrases. These differences suggest that some forms of patronage did not thrive beyond the hothouse of the court; viewed from another perspective, they also suggest that even outside courtly literature, one can retrieve fossils of older forms of patronage in the terms used to describe relationships between leaders and their followers as well as among people more nearly equal in station. A society’s use of social metaphors reveals something of what its members value, what they choose to retain and perpetuate from the past, how they function in moments of crisis, and how successfully their rulers have managed to convince them of the legitimacy of the social and political order. Conversely, the vocabulary of patronage was a social technique that allowed Jews to conduct business, engage in politics and communal regulation, and to amass and retain followers in a variety of spheres, including that of the rabbinic academies who proffered the construction of Judaism that became hegemonic over the course of the Middle Ages.

    Este artículo aborda la cultura pol

  19. Spent nuclear fuel discharges from U.S. reactors 1994

    International Nuclear Information System (INIS)

    1996-02-01

    Spent Nuclear Fuel Discharges from US Reactors 1994 provides current statistical data on fuel assemblies irradiated at commercial nuclear reactors operating in the US. This year's report provides data on the current inventories and storage capacities at these reactors. Detailed statistics on the data are presented in four chapters that highlight 1994 spent fuel discharges, storage capacities and inventories, canister and nonfuel component data, and assembly characteristics. Five appendices, a glossary, and bibliography are also included. 10 figs., 34 tabs

  20. Testing of methods for decontamination of stainless steels and carbon steels conformably to demountable equipment of nuclear power plant with WWR type reactor

    International Nuclear Information System (INIS)

    Dergunova, G.M.; Nazarov, V.K.; Ozolin, A.B.; Smirnov, L.M.; Stel'mashuk, V.P.; Yulikov, E.I.; Vlasov, I.N.

    1978-01-01

    Results are given of experiments on decontamination of stainless steel by the oxidation-reduction method and also results of decontamination of carbon steel by means of solutions based on oxalic acid, citric acid and phosphoric acid. Investigations of efficiency of oxidation-reduction treatment were done on samples of stainless steel cut from the pipeline of the primary coolant circuit of reactor. Comparison is given of efficiency of oxidation-reduction methods of contamination of stainless steel in the case of application of different compositions of decontaminating solutions. Dependences are given for decontamination completeness on duration of operations, on temperature and on ratio of volume of decontaminating solutions to surface are of the sample. For carbon steels parameters are given for decontamination process by means of oxalic, citric and phosphoric acid solutions. (I.T.) [ru

  1. U.S. technology for mechanized/automated fabrication of fast reactor fuel

    International Nuclear Information System (INIS)

    Nyman, D.H.; Bennett, D.W.; Claudson, T.T.; Dahl, R.E.; Graham, R.A.; Keating, J.J.; Yatabe, J.M.

    1978-01-01

    The status of the U.S. fast reactor Fuel Fabrication Development Program is discussed. The objectives of the program are to develop and evaluate a high throughput pilot fuel fabrication line including close-coupled chemistry and wet scrap recycle operations. The goals of the program are to demonstrate by mechanized/automated and remote processes: reduced personnel exposure, enhanced safegurads/accountability, improved fuel performance, representative fabrication rates and reduced fuel costs

  2. The nuclear reactor strategy between fast breeder reactors and advanced pressurized water reactors

    International Nuclear Information System (INIS)

    Seifritz, W.

    1983-01-01

    A nuclear reactor strategy between fast breeder reactors (FBRs) and advanced pressurized water reactors (APWRs) is being studied. The principal idea of this strategy is that the discharged plutonium from light water reactors (LWRs) provides the inventories of the FBRs and the high-converter APWRs, whereby the LWRs are installed according to the derivative of a logistical S curve. Special emphasis is given to the dynamics of reaching an asymptotic symbiosis between FBRs and APWRs. The main conclusion is that if a symbiotic APWR-FBR family with an asymptotic total power level in the terawatt range is to exist in about half a century from now, we need a large number of FBRs already in an early phase

  3. Aging management of PWR reactor internals in U.S. plants

    International Nuclear Information System (INIS)

    Amberge, K.J.; Demma, A.

    2015-01-01

    This paper describes the development, aging management strategies and inspection results of the Pressurized Water Reactor (PWR) vessel internals inspection and evaluation guidelines. The goal of these guidelines is to provide PWR owners with robust aging management strategies to monitor degradation of internals components to support life extension as well as the current period of operation and power up-rate activities. The implementation of these guidelines began in 2010 within the U.S. PWR fleet and several examinations have been performed since. Examples of inspection results are presented for selected vessel internals components and are compared with simulation results. In summary, to date there have been no observations of austenitic stainless steel stress corrosion cracking (SCC), which is consistent with expectations based on the current understanding of the mechanism. Observations of irradiation assisted stress corrosion cracking (IASCC) have been limited and only found in baffle former bolting. Additionally, no macroscopic effects or global observations of void swelling impacts on general conditions of reactor internal hardware have been observed. (authors)

  4. U.S. Status of Fast Reactor Research and Technology

    International Nuclear Information System (INIS)

    Hill, Robert

    2012-01-01

    Summary: • Fast reactor R&D is focused on key technologies innovations for performance improvement (cost reduction) and safety: 1. System Integration and Concept Development; 2. Safety Technology; 3. Advanced Materials; 4. Ultrasonic Viewing; 5. Advanced Energy Conversion (Supercritical CO 2 Brayton cycle); 6. Reactor Simulation; 7. Nuclear Data; 8. Advanced Fuels. • Fast reactors have flexible capability for actinide management: – A wide variety of fuel cycle options are being considered; • International R&D collaboration pursued in Generation-IV and multilateral arrangements

  5. Neutron diffraction radiation of solid solution of carbon and hydrogen in the α-titanium in the homogeneity domain

    International Nuclear Information System (INIS)

    Mirzaev, B.B.; Khidirov, I.; Mukhtarova, N.N.

    2005-01-01

    In the work by the neutron-graph the homogeneity domain of the introduction solid solution TiC x H y is determined. The sample neutron grams have been taken on the neutron diffractometer (λ=.1085 nm) installed at the thermal column of the WWR-SM reactor (INF AN RUz). For the phase analysis and estimation of solid solutions homogeneity the X-ray graph was used. X-ray grams were taken on the X-ray diffractometer DRON-3M with use of CuK α radiation (λ=0.015418 nm)

  6. Air pollution impact on aerosol variability over mega cities using remote sensing technology: case study, Cairo, Egypt

    International Nuclear Information System (INIS)

    El-Askary, H.

    2006-01-01

    Air pollution problems over mega cities differ greatly and are influenced by a number of factors, including topography, demography, meteorology, level and rate of industrialization and socioeconomic development. Cairo is considered a key city for economy, education, politics industry and technology in the Middle East.Increasing business and industrial activities in the city accompanied by shortage of the institutional capabilities for monitoring and control, in addition to environmental impact negligence that prevails over many of the production sectors, have contributed to excessive air pollution problems that have reached the level of crisis. A contributor to this problem is natural and man made effects such as dust and aerosols uptakes. Such pollution episodes are observed during the months of October showing the so called B lack Cloud . Such pollution leads to wide variability of aerosols behavior over Cairo. Hence, aerosol related parameters obtained from satellite measurements have been studied here. Aerosol optical depth (AOD) behavior showed a dual maxima nature in each year from 2000 till 2005 during the months of (April, May) and October confirming dust and air pollution events, respectively. Such behavior is confirmed by the high negative correlation with the aerosol fine mode fraction (FMF) reaching -0.75. FMF product confirms a higher value during the months of October representing the Black Cloud episodes due to fine particles contribution in these events rather than during the dust events. However, lower values are observed in the last two years due to the new control measures enforced by the government for the environment protection. The difference between the AOD and FMF showed a higher contribution of the fine grains during the Black Cloud events rather than coarser grains during dust events as expected. Among the sources known to contribute to the black cloud formation is the fire burns over the Nile Delta region during the months of September

  7. Reactor container

    International Nuclear Information System (INIS)

    Naruse, Yoshihiro.

    1990-01-01

    The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

  8. Optimum Signal Processing in Distributed Sensor Systems.

    Science.gov (United States)

    1987-12-01

    Magdy G. EI-Sheimy 317, King Faesal St., Madkor Station, Pyramid "- -: Giza , Egypt 31. Colonel Salah M. El-MYagraby Building 3S, Apt. 21. Tawfeck City...155--51. UAE University. Al-Amn United Arab Eirates 19. Prof. Abdel-N-ahaab Fayez Faculty of Engineering, Cairo University Giza , Egyvpt 20. Prof. P. K...Library, Military Technical College Koprey EI-qubaa Cairo, Egypt 27. Library, Faculty of Engineering Cairo University Giza , Egypt 2S. Lieutenant

  9. DIRECT ENERGY CONVERSION (DEC) FISSION REACTORS - A U.S. NERI PROJECT

    International Nuclear Information System (INIS)

    Beller, D.; Polansky, G.

    2000-01-01

    The direct conversion of the electrical energy of charged fission fragments was examined early in the nuclear reactor era, and the first theoretical treatment appeared in the literature in 1957. Most of the experiments conducted during the next ten years to investigate fission fragment direct energy conversion (DEC) were for understanding the nature and control of the charged particles. These experiments verified fundamental physics and identified a number of specific problem areas, but also demonstrated a number of technical challenges that limited DEC performance. Because DEC was insufficient for practical applications, by the late 1960s most R and D ceased in the US. Sporadic interest in the concept appears in the literature until this day, but there have been no recent programs to develop the technology. This has changed with the Nuclear Energy Research Initiative that was funded by the U.S. Congress in 1999. Most of the previous concepts were based on a fission electric cell known as a triode, where a central cathode is coated with a thin layer of nuclear fuel. A fission fragment that leaves the cathode with high kinetic energy and a large positive charge is decelerated as it approaches the anode by a charge differential of several million volts, it then deposits its charge in the anode after its kinetic energy is exhausted. Large numbers of low energy electrons leave the cathode with each fission fragment; they are suppressed by negatively biased on grid wires or by magnetic fields. Other concepts include magnetic collimators and quasi-direct magnetohydrodynamic generation (steady flow or pulsed). We present the basic principles of DEC fission reactors, review the previous research, discuss problem areas in detail and identify technological developments of the last 30 years relevant to overcoming these obstacles. A prognosis for future development of direct energy conversion fission reactors will be presented

  10. Advanced boiling water reactors for the 90's and beyond

    International Nuclear Information System (INIS)

    Rao, A.S.; Sawyer, C.D.; Qurik, J.F.; McCandless, R.J.

    1990-01-01

    This paper discusses how the advanced boiling water reactor (ABWR) is being developed by an international team of BWR manufacturers to respond to worldwide utility needs in the 1990s. Major objectives of the ABWR program are design simplification; improved safety and reliability; reduced construction, fuel and operating costs; improved maneuverability and reduced occupational exposure and radwaste. International cooperative efforts are also under way aimed at development of a simplified BWR employing natural circulation and passive safety systems. The SBWR conceptual design is complete. This BWR concept shows technical and economic promise. The SBWR program is aimed at providing a U.S. NRC certified design in an investor-ready state by 1995. With its short construction schedule, the 600 MWe SBWR will provide an option for commercial operation worldwide by the mid-to-late 1990s

  11. Integral Inherently Safe Light Water Reactor (I2S-LWR)

    Energy Technology Data Exchange (ETDEWEB)

    Petrovic, Bojan [Georgia Inst. of Technology, Atlanta, GA (United States); Memmott, Matthew [Brigham Young Univ., Provo, UT (United States); Boy, Guy [Florida Inst. of Technology, Melbourne, FL (United States); Charit, Indrajit [Univ. of Idaho, Moscow, ID (United States); Manera, Annalisa [Univ. of Michigan, Ann Arbor, MI (United States); Downar, Thomas [Univ. of Michigan, Ann Arbor, MI (United States); Lee, John [Univ. of Michigan, Ann Arbor, MI (United States); Muldrow, Lycurgus [Morehouse College, Atlanta, GA (United States); Upadhyaya, Belle [Univ. of Tennessee, Knoxville, TN (United States); Hines, Wesley [Univ. of Tennessee, Knoxville, TN (United States); Haghighat, Alierza [Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States)

    2017-10-02

    This final report summarizes results of the multi-year effort performed during the period 2/2013- 12/2016 under the DOE NEUP IRP Project “Integral Inherently Safe Light Water Reactors (I2S-LWR)”. The goal of the project was to develop a concept of a 1 GWe PWR with integral configuration and inherent safety features, at the same time accounting for lessons learned from the Fukushima accident, and keeping in mind the economic viability of the new concept. Essentially (see Figure 1-1) the project aimed to implement attractive safety features, typically found only in SMRs, to a larger power (1 GWe) reactor, to address the preference of some utilities in the US power market for unit power level on the order of 1 GWe.

  12. A positive psychology to cope with radicalisation and terrorism? A case study of the speech by Barack Obama at Cairo

    Directory of Open Access Journals (Sweden)

    Manuel Moyano

    2016-12-01

    Full Text Available Since the September 11 terrorist attacks, coping with radicalisation and jihadist terrorism has been at the forefront of the domestic and foreign policy agendas in Western societies. During this time, the influence that political leaders can exert in their interaction with institutions, citizens, and terrorist organizations has been demonstrated. We present a case study of the speech by Barak Obama on June 4, 2009 at the University of Cairo (“A New Beginning”. Its content and internal structure is analysed using the classification of virtues and strengths defined by Peterson and Seligman (2004 as a theoretical and conceptual reference within the framework of positive psychology. This speech marked a turning point in the relationship between the USA and the Arab-Muslim world and could be considered to be a genuine exercise in positive communication. Its implications are yet to be determined, because it continues to exert an influence on the Obama administration’s domestic and foreign policy. In a globalized and networking world in which risks and adversities require innovative responses, more than ever we suggest that social communication capable of promoting virtues and strengths associated with optimism, hope, confidence, strength, or vitality is needed more than ever.

  13. Engineering progress of CNS concept in Hanaro

    International Nuclear Information System (INIS)

    Choi, C.O.; Park, K.N.; Park, S.H.

    1997-01-01

    The Korea Atomic Energy research Institute (KAERI) strives to provide utilizing facilities on and around the Hanaro reactor in order to activate advanced researches by neutron application. As one of the facilities to be installed, the conceptual design work of CNS was started in 1996 with a project schedule of 5 years so that its installation work can be finished by the year 2000. And the major engineering targets of this CNS facility are established for a minimum physical interference with the present facilities of the Hanaro, a reach-out of very-high-gain factors in the cold neutron flux, a simplicity of the maintenance of the facility, and a safety in the operation of the facility as well as the reactor. For the conceptual design of Hanaro CNS, the experience of utilization and production of cold neutron at WWR-M reactor Gatchina, Russia has been used with that of elaborations for PIK reactor in design for neutron guide systems and instruments. (author)

  14. An Approach to Microanalysis and Conservation of Silver - Copper Object in Agriculture Museum, Cairo, Egypt

    Directory of Open Access Journals (Sweden)

    prof.ABEER Gharib

    2013-01-01

    Full Text Available This research dealt examining, analysis and treatment of a silver - copper belt, it exhibited in Agriculture Museum in Cairo. This research aims to study the ancient silver alloy; because of the successful examination and analysis helps in the treatment of old metal objects and then maintain them. The analysis of archaeological objects requires simultaneously non-destructive (the objects are unique and precious, versatile (samples with different geometry, sensitive (trace elements are often important and multi-elemental methods. In this paper, scanning electron microscopy (SEM employed to diagnose the characteristic morphology and environmental effects of the silver-copper object. X- Ray diffraction (XRD used to identify the mineralogical composition of samples, inductively coupled plasma optical emission spectrometer (ICP used to determine the accurate elemental composition of the silver-copper object. The results obtained by this research showed that the alloy containing about 22% silver, 65% copper, and it covered with copper corrosion products, these results represent the correct diagnosis, which will help us to understand the fabrication of ancient silver-copper alloy, which is still needed more studies.

  15. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

  16. Elemental analysis of two Egyptian iron ores and produced industrial iron samples by neutron activation analysis

    International Nuclear Information System (INIS)

    Sroor, A.; Abdel-Basset, N.; Abdel-Haleem, A.S.; Hassan, A.M.

    2001-01-01

    Elemental analysis of two iron ores and initial industrial iron production prepared by the Egyptian Iron and Steel Company of Helwan near Cairo were performed by the instrumental neutron activation analysis technique. Five samples of each type were irradiated for 48 h in a thermal neutron flux of 4x10 12 n/cm 2 s in the first Egyptian research reactor ET-RR-1. Also, the Pneumatic Irradiation Rabbit System (PIRS), attached to the reactor ET-RR-1 in Inshass, was used to measure short-life elements. The γ-ray spectra were obtained with a hyper pure germanium detection system. The concentration percentage values of major, minor and trace elements are presented. Implications of the elemental concentration values obtained are presented

  17. A randomised phase III study on capecitabine, oxaliplatin and bevacizumab with or without cetuximab in first-line advanced colorectal cancer, the CAIRO2 study of the Dutch Colorectal Cancer Group (DCCG). An interim analysis of toxicity

    NARCIS (Netherlands)

    Tol, J.; Koopman, M.; Rodenburg, C. J.; Cats, A.; Creemers, G. J.; Schrama, J. G.; Erdkamp, F. L. G.; Vos, A. H.; Mol, L.; Antonini, N. F.; Punt, C. J. A.

    2008-01-01

    Targeting the vascular endothelial growth factor or the epidermal growth factor receptor (EGFR) has shown efficacy in advanced colorectal cancer (ACC), but no data are available on the combination of these strategies with chemotherapy in the first-line treatment. The CAIRO2 study evaluates the

  18. New perspectives on population: lessons from Cairo.

    Science.gov (United States)

    Ashford, L S

    1995-03-01

    The lessons from the 1994 World Population Conference in Cairo, Egypt, are summarized in this publication. The topics of discussion include the evolution of population policies, the changing policy environment, demographic trends, and solutions in the form of gender equity, provision of reproductive health services, and sustainable social and economic development. The program of action supported by 180 governments and targeted for 2015 articulated the goals of universal access to a full range of safe and reliable family planning methods and reproductive health services, a specified level of reduction in infant and child mortality, a specified level of reduction in maternal mortality, an increase in life expectancy to 70-75 years or more, and universal access to and completion of primary education. Other features include goals for improving women's status and equity in gender relations, expansion of educational and job opportunities for women and girls, and involvement of men in childrearing responsibilities and family planning. Steps should be taken to eliminate poverty and reduce or eliminate unsustainable patterns of production and consumption. Population policy must be integrated within social and economic development policies. About $22 billion will be needed for provision of family planning and reproductive health services by the year 2015. Costs will increase over the 10-year period due to the increased population to be served. Per person user costs for family planning alone are higher in countries without infrastructure and technical skills. Actual costs vary with the cost of contraceptive supplies, patterns of use, and efficiency of delivery systems. Although the plan offers 16 chapters worth of advice and recommends 243 specific actions, countries will have to be selective due to cost limitations. The 20/20 Initiative is proposed for sharing social service costs between international donors (20%) and host countries (20%). A separate UN projection of need

  19. Successive and large-scale synthesis of InP/ZnS quantum dots in a hybrid reactor and their application to white LEDs

    Science.gov (United States)

    Kim, Kyungnam; Jeong, Sohee; Woo, Ju Yeon; Han, Chang-Soo

    2012-02-01

    We report successive and large-scale synthesis of InP/ZnS core/shell nanocrystal quantum dots (QDs) using a customized hybrid flow reactor, which is based on serial combination of a batch-type mixer and a flow-type furnace. InP cores and InP/ZnS core/shell QDs were successively synthesized in the hybrid reactor in a simple one-step process. In this reactor, the flow rate of the solutions was typically 1 ml min-1, 100 times larger than that of conventional microfluidic reactors. In order to synthesize high-quality InP/ZnS QDs, we controlled both the flow rate and the crystal growth temperature. Finally, we obtained high-quality InP/ZnS QDs in colors from bluish green to red, and we demonstrated that these core/shell QDs could be incorporated into white-light-emitting diode (LED) devices to improve color rendering performance.

  20. Report of the first meeting of the Project Advisory Committee (Technical) 21-24 March 1983, at NEMROCK, Cairo

    International Nuclear Information System (INIS)

    Taylor, C.B.G.

    1983-05-01

    The Project Advisory Committee (Technical) (PACT) met on 21-24 March 1983, at NEMROCK, Cairo, Egypt, to discuss the joint IAEA/WHO project on Intracavitary Radiation Therapy for Cancer of the Uterus (Egypt/6/004). At this four day meeting the committee (1) identified a well-defined administrative framework in which earlier diagnosis of uterine cancer may be organized, on a limited but firm basis. (2) Agreed on the clinical and dosimetric principles to be followed in implementing the project. (3) Decided on the types and quantities of equipment which it will need in its first two years. (4) Developed the outline of the syllabus for the first training course, and fixed its date (three weeks from 83-10-29). (5) Reviewed the costs which will be incurred in carrying through the project and found them to be consistent with the funds available

  1. Application of S-CO_2 Cycle for Small Modular Reactor coupled with Desalination System

    International Nuclear Information System (INIS)

    Lee, Won Woong; Bae, Seong Jun; Lee, Jeong Ik

    2016-01-01

    The Korean small modular reactor, SMART (System-integrated Modular Advanced ReacTor, 100MWe), is designed to achieve enhanced safety and improved economics through reliable passive safety systems, a system simplification and component modularization. SMART can generate electricity and provide water by seawater desalination. However, due to the desalination aspect of SMART, the total amount of net electricity generation is decreased from 100MWe to 90MWe. The authors suggest in this presentation that the reduction of electricity generation can be replenished by applying S-CO_2 power cycle technology. The S-CO_2 Brayton cycle, which is recently receiving significant attention as the next generation power conversion system, has some benefits such as high cycle efficiency, simple configuration, compactness and so on. In this study, the cycle performance analysis of the S-CO_2 cycles for SMART with desalination system is conducted. The simple recuperated S-CO_2 cycle is revised for coupling with desalination system. The three revised layout are proposed for the cycle performance comparison. In this results of the 3rd revised layout, the cycle efficiency reached 37.8%, which is higher than the efficiency of current SMART with the conventional power conversion system 30%

  2. Getting into hot water Problematizing hot water service demand: The case of Old Cairo

    Science.gov (United States)

    Culhane, Thomas Henry

    This dissertation analyzes hot water demand and service infrastructure in two neighboring but culturally distinct communities of the urban poor in the inner-city area of central Cairo. The communities are the Historic Islamic Cairo neighborhood of Darb Al Ahmar at the foot of Al-Azhar park, and the Zurayib neighborhood of Manshiyat Nasser where the Coptic Zabaleen Recyclers live. The study focuses on the demand side of the hot water issue and involves consideration of built-environment infrastructures providing piped water, electricity, bottled gas, sewage, and the support structures (wiring and plumbing) for consumer durables (appliances such as hot water heaters, stoves, refrigerators, air conditioners) as well as water pumps and water storage tanks. The study asks the questions "How do poor communities in Cairo value hot water" and "How do cost, infrastructure and cultural preferences affect which attributes of hot water service are most highly preferred?". To answer these questions household surveys based primarily on the World Bank LSMS modules were administered by professional survey teams from Darb Al Ahmar's Aga Khan Trust for Culture and the Zabaleen's local NGO "Spirit of Youth" in their adjacent conununities in and surrounding historic Cairo. In total 463 valid surveys were collected, (231 from Darb Al Ahmar, 232 from the Zabaleen). The surveys included a contingent valuation question to explore Willingness to Pay for improved hot water service; the surveys queried household assets as proxies for income. The dissertation's findings reveal that one quarter of the residents of Darb Al Ahmar and two-thirds of the residents of Manshiyet Nasser's Zabaleen lack conventional water heating service. Instead they employ various types of stoves and self-built contraptions to heat water, usually incurring considerable risk and opportunity costs. However the thesis explores the notion that this is rational "satisficing" behavior; despite the shortcomings of such self

  3. Recent progress in stellarator reactor conceptual design

    International Nuclear Information System (INIS)

    Miller, R.L.

    1985-01-01

    The Stellarator/Torsatron/Heliotron (S/T/H) class of toroidal magnetic fusion reactor designs continues to offer a distinct and in several ways superior approach to eventual commercial competitiveness. Although no major, integrated conceptual reactor design activity is presently underway, a number of international research efforts suggest avenues for the substantial improvement of the S/T/H reactor embodiment, which derive from recent experimental and theoretical progress and are responsive to current trends in fusion-reactor projection to set the stage for a third generation of designs. Recent S/T/H reactor design activity is reviewed and the impact of the changing technical and programmatic context on the direction of future S/T/H reactor design studies is outlined

  4. Work Breakdown Structure and Work Packages for Decommissioning the Nuclear Research Reactor VVR-S Magurele-Bucharest

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2013-06-15

    The research reactor type VVR-S (tank type, water cooled, moderator and reflector, thermal power 2 MW, thermal energy 9.52 GWd) was put into service in July 1957, and in December 1997, was shut down. In 2002, the Romanian Government decided to put the research reactor into a permanent shutdown condition in order to start decommissioning. This nuclear facility had been used in nuclear research and radioisotope production for 40 years without any events, incidents or accidents. At the same site, in the immediate vicinity of the research reactor, there are many other nuclear facilities: a radioactive waste treatment plant, a tandem Van de Graaff heavy ion accelerator, a cyclotron, an industrial irradiator and a radioisotope production centre.

  5. Application of LiF for determining the gamma-radiation characteristics of the shut-down reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ibragimova, E M; Musaeva, M A; Ashrapov, U T; Kalanov, M U; Muminov, M I [Inst. of Nuclear Physics, Tashkent (Uzbekistan)

    2005-07-01

    Full text: The power of {sup 60}Co {approx}1.25 MeV gamma-radiation source at the INP AS RUz is limited by 8 Gy/s, which does not satisfy several tasks of material science now. Therefore, we were first to suggest the irradiation of materials with gamma-rays of 0.1-7 MeV, which are emitted by the uranium fission products ({sup 41}Ar, {sup 135}Xe, {sup 125}Xe, {sup 125}I,{sup 137}Cs, {sup 134}Cs, {sup 144}Ce, {sup 95}Zr, {sup 140}Ba, {sup 140}La, {sup 99}Mo, {sup 60}Co) and {sup l6}N, {sup 24}Na, {sup 28}Al radio-nuclides in water during prophylactic shut-downs of our nuclear reactor WWR-SM. The gamma-dose rate kinetics was monitored with the ion current in ionization chambers KNK-53M fixed outside the reactor core from the stop-moment. The current kinetics comprised 4 steps with a high reproducibility at 2 and 0.5 {mu}A, then 50 and 10 nA, each lasting for 1,10, 40 and up to 200 hours, according to the isotope life-times. LiF crystal is known as a thermal luminescence dosimeter of mixed radiations up to 100 Gy. Yet in this work the absorbed gamma-energy dose D{sub {gamma}} was determined by accumulation of the known stable structure defects in thin cleaved LiF crystals: by induced optical absorption and luminescence of F- and M-centers. The samples were irradiated in Al-containers filled with water to keep the temperature of {approx}40 deg. C in the time range from 30 minutes to 150 hours. Optical absorption spectra were registered at spectrometer Specord M-40. Then the induced color center concentration was calculated by the Smakula relation, which is proportional to the absorbed dose D{gamma}. For a better reliability the photoluminescence center content was also determined. Selecting comparable close intensities of the induced absorption and luminescence bands obtained after irradiations of LiF references in the certified {sup 60}Co gamma-sources of the known gamma fluxes 0.7 and 7.5 Gy/s, the gamma-radiation intensity of the shut-down reactor was estimated in

  6. Application of LiF for determining the gamma-radiation characteristics of the shut-down reactor

    International Nuclear Information System (INIS)

    Ibragimova, E.M.; Musaeva, M.A.; Ashrapov, U.T.; Kalanov, M.U.; Muminov, M.I.

    2005-01-01

    Full text: The power of 60 Co ∼1.25 MeV gamma-radiation source at the INP AS RUz is limited by 8 Gy/s, which does not satisfy several tasks of material science now. Therefore, we were first to suggest the irradiation of materials with gamma-rays of 0.1-7 MeV, which are emitted by the uranium fission products ( 41 Ar, 135 Xe, 125 Xe, 125 I, 137 Cs, 134 Cs, 144 Ce, 95 Zr, 140 Ba, 140 La, 99 Mo, 60 Co) and l6 N, 24 Na, 28 Al radio-nuclides in water during prophylactic shut-downs of our nuclear reactor WWR-SM. The gamma-dose rate kinetics was monitored with the ion current in ionization chambers KNK-53M fixed outside the reactor core from the stop-moment. The current kinetics comprised 4 steps with a high reproducibility at 2 and 0.5 μA, then 50 and 10 nA, each lasting for 1,10, 40 and up to 200 hours, according to the isotope life-times. LiF crystal is known as a thermal luminescence dosimeter of mixed radiations up to 100 Gy. Yet in this work the absorbed gamma-energy dose D γ was determined by accumulation of the known stable structure defects in thin cleaved LiF crystals: by induced optical absorption and luminescence of F- and M-centers. The samples were irradiated in Al-containers filled with water to keep the temperature of ∼40 deg. C in the time range from 30 minutes to 150 hours. Optical absorption spectra were registered at spectrometer Specord M-40. Then the induced color center concentration was calculated by the Smakula relation, which is proportional to the absorbed dose Dγ. For a better reliability the photoluminescence center content was also determined. Selecting comparable close intensities of the induced absorption and luminescence bands obtained after irradiations of LiF references in the certified 60 Co gamma-sources of the known gamma fluxes 0.7 and 7.5 Gy/s, the gamma-radiation intensity of the shut-down reactor was estimated in correlation with the ion current as 10 nA = 15 Gy/s. At short times of irradiation the linear dose dependence

  7. Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

    International Nuclear Information System (INIS)

    1975-06-01

    The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

  8. Update on reactors and reactor instruments in Asia

    Science.gov (United States)

    Rao, K. R.

    1991-10-01

    The 1980s have seen the commissioning of several medium flux (∼10 14 neutrons/cm 2s) research reactors in Asia. The reactors are based on indigenous design and development in India and China. At Dhruva reactor (India), a variety of neutron spectrometers have been established that have provided useful data related to the structure of high- Tc materials, phonon density of states, magnetic moment distributions and micellar aggregation during the last couple of years. Polarised neutron analysis, neutron interferometry and neutron spin echo methods are some of the new techniques under development. The spectrometers and associated automaton, detectors and neutron guides have all been indigenously developed. This paper summarises the developments and on-going activities in Bangladesh, China, India, Indonesia, Korea, Malaysia, the Philippines and Thailand.

  9. Update on reactors and reactor instruments in Asia

    International Nuclear Information System (INIS)

    Rao, K.R.

    1991-01-01

    The 1980s have seen the commissioning of several medium flux (∝10 14 neutrons/cm 2 s) research reactors in Asia. The reactors are based on indigenous design and development in India and China. At Dhruva reactor (India), a variety of neutron spectrometers have been established that have provided useful data related to the structure of high-Tc materials, phonon density of states, magnetic moment distributions and micellar aggregation during the last couple of years. Polarised neutron analysis, neutron interferometry and neutron spin echo methods are some of the new techniques under development. The spectrometers and associated automaton, detectors and neutron guides have all been indigenously developed. This paper summarises the developments and on-going activities in Bangladesh, China, India, Indonesia, Korea, Malaysia, the Philippines and Thailand. (orig.)

  10. Internet accessible hot cell with gamma spectroscopy at the Missouri S and T nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Grant, Edwin [Nuclear Engineering, Missouri University of Science and Technology, 203 Fulton Hall, 300 W. 13th St., Rolla, MO 65409 (United States); Mueller, Gary, E-mail: gmueller@mst.edu [Nuclear Engineering, Missouri University of Science and Technology, 203 Fulton Hall, 300 W. 13th St., Rolla, MO 65409 (United States); Castano, Carlos; Usman, Shoaib; Kumar, Arvind [Nuclear Engineering, Missouri University of Science and Technology, 203 Fulton Hall, 300 W. 13th St., Rolla, MO 65409 (United States)

    2011-08-15

    Highlights: > A dual-chambered internet-accessible heavily shielded facility has been built. > The facility allows distance users to analyze neutron irradiated samples remotely. > The Missouri S and T system uses computer automation with user feedback. > The system can analyze multiple samples and assist several researchers concurrently. - Abstract: A dual-chambered internet-accessible heavily shielded facility with pneumatic access to the University of Missouri Science and Technology (Missouri S and T) 200 kW Research Nuclear Reactor (MSTR) core has been built and is currently available for irradiation and analysis of samples. The facility allows authorized distance users engaged in collaborative activities with Missouri S and T to remotely manipulate and analyze neutron irradiated samples. The system consists of two shielded compartments, one for multiple sample storage, and the other dedicated exclusively for radiation measurements and spectroscopy. The second chamber has multiple detector ports, with graded shielding, and has the capability to support gamma spectroscopy using radiation detectors such as an HPGe detector. Both these chambers are connected though a rapid pneumatic system with access to the MSTR nuclear reactor core. This new internet-based system complements the MSTR's current bare pneumatic tube (BPT) and cadmium lined pneumatic tube (CPT) facilities. The total transportation time between the core and the hot cell, for samples weighing 10 g, irradiated in the MSTR core, is roughly 3.0 s. This work was funded by the DOE grant number DE-FG07-07ID14852 and expands the capabilities of teaching and research at the MSTR. It allows individuals who do not have on-site access to a nuclear reactor facility to remotely participate in research and educational activities.

  11. Successive and large-scale synthesis of InP/ZnS quantum dots in a hybrid reactor and their application to white LEDs

    International Nuclear Information System (INIS)

    Kim, Kyungnam; Jeong, Sohee; Woo, Ju Yeon; Han, Chang-Soo

    2012-01-01

    We report successive and large-scale synthesis of InP/ZnS core/shell nanocrystal quantum dots (QDs) using a customized hybrid flow reactor, which is based on serial combination of a batch-type mixer and a flow-type furnace. InP cores and InP/ZnS core/shell QDs were successively synthesized in the hybrid reactor in a simple one-step process. In this reactor, the flow rate of the solutions was typically 1 ml min −1 , 100 times larger than that of conventional microfluidic reactors. In order to synthesize high-quality InP/ZnS QDs, we controlled both the flow rate and the crystal growth temperature. Finally, we obtained high-quality InP/ZnS QDs in colors from bluish green to red, and we demonstrated that these core/shell QDs could be incorporated into white-light-emitting diode (LED) devices to improve color rendering performance. (paper)

  12. U.S. NRC training for research and training reactor inspectors

    International Nuclear Information System (INIS)

    Sandquist, G.M.; Kunze, J.F.

    2011-01-01

    Currently, a large number of license activities (Early Site Permits, Combined Operating License, reactor certifications, etc.), are pending for review before the United States Nuclear Regulatory Commission (US NRC). Much of the senior staff at the NRC is now committed to these review and licensing actions. To address this additional workload, the NRC has recruited a large number of new Regulatory Staff for dealing with these and other regulatory actions such as the US Fleet of Research and Test Reactors (RTRs). These reactors pose unusual demands on Regulatory Staff since the US Fleet of RTRs, although few (32 Licensed RTRs as of 2010), they represent a broad range of reactor types, operations, and research and training aspects that nuclear reactor power plants (such as the 104 LWRs) do not pose. The US NRC must inspect and regulate all these entities. This paper addresses selected training topics and regulatory activities provided US NRC Inspectors for US RTRs. (author)

  13. Stylized whole-core benchmark of the Integral Inherently Safe Light Water Reactor (I2S-LWR) concept

    International Nuclear Information System (INIS)

    Hon, Ryan; Kooreman, Gabriel; Rahnema, Farzad; Petrovic, Bojan

    2017-01-01

    Highlights: • A stylized benchmark specification of the I2S-LWR core. • A library of cross sections were generated in both 8 and 47 groups. • Monte Carlo solutions generated for the 8 group library using MCNP5. • Cross sections and pin fission densities provided in journal’s repository. - Abstract: The Integral, Inherently Safe Light Water Reactor (I 2 S-LWR) is a pressurized water reactor (PWR) concept under development by a multi-institutional team led by Georgia Tech. The core is similar in size to small 2-loop PWRs while having the power level of current large reactors (∼1000 MWe) but using uranium silicide fuel and advanced stainless steel cladding. A stylized benchmark specification of the I 2 S-LWR core has been developed in order to test whole-core neutronics codes and methods. For simplification the core was split into 57 distinct material regions for cross section generation. Cross sections were generated using the lattice physics code HELIOS version 1.10 in both 8 and 47 groups. Monte Carlo solutions, including eigenvalue and pin fission densities, were generated for the 8 group library using MCNP5. Due to space limitations in this paper, the full cross section library and normalized pin fission density results are provided in the journal’s electronic repository.

  14. Fourth Generation Reactor Concepts

    International Nuclear Information System (INIS)

    Furtek, A.

    2008-01-01

    Concerns over energy resources availability, climate changes and energy supply security suggest an important role for nuclear energy in future energy supplies. So far nuclear energy evolved through three generations and is still evolving into new generation that is now being extensively studied. Nuclear Power Plants are producing 16% of the world's electricity. Today the world is moving towards hydrogen economy. Nuclear technologies can provide energy to dissociate water into oxygen and hydrogen and to production of synthetic fuel from coal gasification. The introduction of breeder reactors would turn nuclear energy from depletable energy supply into an unlimited supply. From the early beginnings of nuclear energy in the 1940s to the present, three generations of nuclear power reactors have been developed: First generation reactors: introduced during the period 1950-1970. Second generation: includes commercial power reactors built during 1970-1990 (PWR, BWR, Candu, Russian RBMK and VVER). Third generation: started being deployed in the 1990s and is composed of Advanced LWR (ALWR), Advanced BWR (ABWR) and Passive AP600 to be deployed in 2010-2030. Future advances of the nuclear technology designs can broaden opportunities for use of nuclear energy. The fourth generation reactors are expected to be deployed by 2030 in time to replace ageing reactors built in the 1970s and 1980s. The new reactors are to be designed with a view of the following objectives: economic competitiveness, enhanced safety, minimal radioactive waste production, proliferation resistance. The Generation IV International Forum (GIF) was established in January 2000 to investigate innovative nuclear energy system concepts. GIF members include Argentina, Brazil, Canada, Euratom, France Japan, South Africa, South Korea, Switzerland, United Kingdom and United States with the IAEA and OECD's NEA as permanent observers. China and Russia are expected to join the GIF initiative. The following six systems

  15. Reactor building

    International Nuclear Information System (INIS)

    Ebata, Sakae.

    1990-01-01

    At least one valve rack is disposed in a reactor building, on which pipeways to a main closure valve, valves and bypasses of turbines are placed and contained. The valve rack is fixed to the main body of the building or to a base mat. Since the reactor building is designed as class A earthquake-proofness and for maintaining the S 1 function, the valve rack can be fixed to the building main body or to the base mat. With such a constitution, the portions for maintaining the S 1 function are concentrated to the reactor building. As a result, the dispersion of structures of earthquake-proof portion corresponding to the reference earthquake vibration S 1 can be prevented. Accordingly, the conditions for the earthquake-proof design of the turbine building and the turbine/electric generator supporting rack are defined as only the class B earthquake-proof design conditions. In view of the above, the amount of building materials can be saved and the time for construction can be shortened. (I.S.)

  16. Participation in the U.S. Department of Energy Reactor Sharing Program

    International Nuclear Information System (INIS)

    Mulder, R. U.; Benneche, P. E.; Hosticka, B.

    1998-01-01

    The objective of the DOE supported Reactor Sharing Program is to increase the availability of university nuclear reactor facilities to non-reactor-owning educational institutions. The educational and research programs of these users institutions is enhanced by the use of the nuclear facilities

  17. Reactor feedwater system

    International Nuclear Information System (INIS)

    Hikabe, Katsumi.

    1978-01-01

    Purpose: In order to prevent thermal stresses of a core of PWR type reactor, described has been a method for feeding heated recirculating water to the core in the case of the reactor start-up or shut-down. Constitution: A recirculating water is degassed, cleaned up and heated in the steam condensers, and then feeds the water to the reactor, characterized in that heaters are provided in the bypasses of the turbine, so that heated water is constantly supplied to the reactor. (Nakamura, S.)

  18. Reactor Coolant Pump seal issues and their applicability to new reactor designs

    International Nuclear Information System (INIS)

    Ruger, C.J.; Higgins, J.C.

    1993-01-01

    Reactor Coolant Pumps (RCPs) of various types are used to circulate the primary coolant through the reactor in most reactor designs. RCPs generally contain mechanical seals to limit the leakage of pressurized reactor coolant along the pump drive shaft into the containment. The relatively large number of RCP seal and seal auxiliary system failures experienced at US operating plants during the 1970's and early 1980's raised concerns from the US Nuclear Regulatory Commission (NRC) that gross failures may lead to reactor core uncovery and subsequent core damage. Some seal failure events resulted in a loss of primary coolant to the containment at flow rates greater than the normal makeup capacity of Pressurized Water Reactor (PWR) plants. This is an example of RCP seal failures resulting in a small Loss of Coolant Accident (LOCA). This paper discusses observed and potential causes of RCP seal failure and the recommendations for limiting the likelihood of a seal induced small LOCA. Issues arising out of the research supporting these recommendations and subsequent public comments by the utility industry on them, serve as lessons learned, which are applicable to the design of new reactor plants

  19. Reactor building

    International Nuclear Information System (INIS)

    Maruyama, Toru; Murata, Ritsuko.

    1996-01-01

    In the present invention, a spent fuel storage pool of a BWR type reactor is formed at an upper portion and enlarged in the size to effectively utilize the space of the building. Namely, a reactor chamber enhouses reactor facilities including a reactor pressure vessel and a reactor container, and further, a spent fuel storage pool is formed thereabove. A second spent fuel storage pool is formed above the auxiliary reactor chamber at the periphery of the reactor chamber. The spent fuel storage pool and the second spent fuel storage pool are disposed in adjacent with each other. A wall between both of them is formed vertically movable. With such a constitution, the storage amount for spent fuels is increased thereby enabling to store the entire spent fuels generated during operation period of the plant. Further, since requirement of the storage for the spent fuels is increased stepwisely during periodical exchange operation, it can be used for other usage during the period when the enlarged portion is not used. (I.S.)

  20. Soviet New Thinking and the Middle East: Gorbachev’s Arab-Israeli Options

    Science.gov (United States)

    1990-04-02

    A~ abia , 4or examoie, unless there is progress between Moscow and Cairo= One must ~o back to the Arab I n d u s t r i a l i z a t i o n...d ,-ert_=in ~ ,-’ ~ ike t=~ crack the moderate Arab market and mtlst t,e thinking about how t*_ ~ co it. The USSPl end Caqoi U~ abia

  1. Development and applications of reactor noise analysis at Ontario Hydro`s CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Gloeckler, O [Ontario Hydro, Toronto, ON (Canada); Tulett, M V [Ontario Hydro, Pickering, ON (Canada). Pickering Generating Station

    1996-12-31

    In 1992 a program was initiated to establish reactor noise analysis as a practical tool for plant performance monitoring and system diagnostics in Ontario Hydro`s CANDU reactors. Since then, various CANDU-specific noise analysis applications have been developed and validated. The noise-based statistical techniques are being successfully applied as powerful troubleshooting and diagnostic tools to a wide variety of actual operational I and C problems. The dynamic characteristics of critical plant components, instrumentation and processes are monitored on a regular basis. Recent applications of noise analysis include (1) validating the dynamics of in-core flux detectors (ICFDS) and ion chambers, (2) estimating the prompt fraction ICFDs in noise measurements at full power and in power rundown tests, (3) identifying the cause of excessive signal fluctuations in certain flux detectors, (4) validating the dynamic coupling between liquid zone control signals, (5) detecting and monitoring mechanical vibrations of detector tubes induced by moderator flow, (6) estimating the dynamics and response time of RTD (Resistance Temperature Detector) temperature signals, (7) isolating the cause of RTD signal anomalies, (8) investigating the source of abnormal flow signal behaviour, (9) estimating the overall response time of flow and pressure signals, (10) detecting coolant boiling in fully instrumented fuel channels, (11) monitoring moderator circulation via temperature noise, and (12) predicting the performance of shut-off rods. Some of these applications are performed on an as-needed basis. The noise analysis program, in the Pickering-B station alone, has saved Ontario Hydro millions of dollars during its first three years. The results of the noise analysis program have been also reviewed by the regulator (Atomic Energy Control Board of Canada) with favorable results. The AECB have expressed interest in Ontario Hydro further exploiting the use of noise analysis technology. (author

  2. Overview of U.S. Fast Reactor Technology Program

    International Nuclear Information System (INIS)

    Hill, Robert

    2013-01-01

    • Concept development studies guide R&D tasks by evaluating system impact for broad variety of technology options: – Small-scale facilities for R&D on key technology; – No near-term plan for demonstration reactor. • Fast reactor R&D is focused on key technologies innovations for performance improvement (cost reduction): – Advanced Structural Materials; – Advanced Energy Conversion; – Advanced Modeling and Simulation. • Other R&D is conducted to address known technology challenges: – Safety and Licensing; – Fuels Development; – Undersodium Viewing

  3. Experience in using a research reactor for the training of power reactor operators

    International Nuclear Information System (INIS)

    Blotcky, A.J.; Arsenaut, L.J.

    1972-01-01

    A research reactor facility such as the one at the Omaha Veterans Administration Hospital would have much to offer in the way of training reactor operators. Although most of the candidates for the course had either received previous training in the Westinghouse Reactor Operator Training Program, had operated nuclear submarine reactors or had operated power reactors, they were not offered the opportunity to perform the extensive manipulations of a reactor that a small research facility will allow. In addition the AEC recommends 10 research reactor startups per student as a prerequisite for a cold operator?s license and these can easily be obtained during the training period

  4. Seven years of operation of the U. S. geological survey TRIGA reactor

    International Nuclear Information System (INIS)

    Kraker, Pat

    1976-01-01

    February 1976 marks 7 years of operation of the U. S. Geological Survey TRIGA Reactor (GSTR) facility. In these 7 years we have generated more than 5800 MWH's of thermal energy and irradiated more than 47,000 samples for experimenters from the Survey, universities, and other Governmental agencies. Several mechanical and electrical components have required attention. Changes to the technical specifications have included one minor wording change involving the evacuation alarm, a reevaluation of the measurement of argon-41 concentrations, a revision concerning transient-rod maintenance, and a reduction in the frequency of fuel-element measurements. To improve physical security we have increased building security, installed an intrusion alarm, and, most recently, expanded the boundaries of the facility within the building to provide better control access. There also have been major changes to our operating procedures and the initiation of a reactor-operator requalification program. (author)

  5. Industrial structure at research reactor suppliers

    International Nuclear Information System (INIS)

    Roegler, H.-J.; Bogusch, E.; Friebe, T.

    2001-01-01

    Due to the recent joining of the forces of Framatome S. A. from France and the Nuclear Division of Siemens AG Power Generation (KWU) from Germany to a Joint Venture named Framatome Advanced Nuclear Power S.A.S., the issue of the necessary and of the optimal industrial structure for nuclear projects as a research reactor is, was discussed internally often and intensively. That discussion took place also in the other technical fields such as Services for NPPs but also in the field of interest here, i. e. Research Reactors. In summarizing the statements of this presentation one can about state that: Research Reactors are easier to build than NPPs, but not standardised; Research Reactors need a wide spectrum of skills and experiences; to design and build Research Reactors needs an experienced team especially in terms of management and interfaces; Research Reactors need background from built reference plants more than from operating plants; Research Reactors need knowledge of suitable experienced subsuppliers. Two more essential conclusions as industry involved in constructing and upgrading research reactors are: Research Reactors by far are more than a suitable core that generates a high neutron flux; every institution that designs and builds a Research Reactor lacks quality or causes safety problems, damages the reputation of the entire community

  6. ZEEP: Canada's first nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Green, R.E.; Okazaki, A. [retired, Atomic Energy of Canada Limited, Chalk River, Ontario (Canada)

    2015-09-15

    In 1905 Albert Einstein published his historic paper on special relativity, which contained the equation E=mc 2. The significance of this mass-energy relationship became evident with the discovery of nuclear fission in 1939, when it was realized that large amounts of energy would be released in a fission chain reaction. Canadian scientists were involved in this field from the beginning and their efforts resulted in the startup in September 1945 of the ZEEP reactor at Chalk River, the first reactor to go critical outside the USA. In this paper we recall some of the events that led to the construction of ZEEP, and describe the role it played in the development of the Canadian nuclear energy program. (author)

  7. Impact of an infection-control program on nurses' knowledge and attitude in pediatric intensive care units at Cairo University hospitals.

    Science.gov (United States)

    Galal, Yasmine S; Labib, John R; Abouelhamd, Walaa A

    2014-04-01

    Healthcare-associated infection is a prominent problem among patients in pediatric intensive care units (PICU) as it could result in significant morbidity, prolonged hospitalization, and increase in medical care costs. The role of nurses is extremely important in preventing hazards and sequela of healthcare-associated infections. The aim of this study was to assess the effect of a health education program regarding infection-control measures on nurses' knowledge and attitude in PICUs at Cairo University hospitals. This was a pre-post test interventional study in which a convenient sample of 125 nurses was taken from the nursing staff in different PICUs at Cairo University hospitals. The study took place in three phases. In the first phase, the nursing staff's knowledge, attitude and practice concerning infection-control measures were tested using a self-administered pretested questionnaire and an observation checklist. The second phase included health education sessions in the form of powerpoint and video presentations; and in the third phase the nurses' knowledge and attitude on infection-control measures were reassessed. A significantly higher level of knowledge was revealed in the postintervention phase as compared with the preintervention phase with regards to the types of nosocomial infections (94.4 vs. 76.8%, Pcontrol nosocomial infections (89.6 vs. 68%, Pcontrol measures could protect them completely from acquiring infection (79.2 vs. 65.6%, P=0.033). Statistically significant higher total knowledge and attitude scores were revealed in the postintervention phase as compared with the preintervention one (PHospital (88%), whereas it was the lowest in the emergency pediatric unit (65%). There is scope for improvement in knowledge and attitude after educational program was offered to the nursing staff. Educational training programs should be multidisciplinary interventions in the era of quality control to help healthcare workers realize the importance of basic

  8. Direct energy conversion in fission reactors: A U.S. NERI project

    International Nuclear Information System (INIS)

    Slutz, Stephen A.; Seidel, David B.; Polansky, Gary F.; Rochau, Gary E.; Lipinski, Ronald J.; Besenbruch, G.; Brown, L.C.; Parish, T.A.; Anghaie, S.; Beller, D.E.

    2000-01-01

    In principle, the energy released by a fission can be converted directly into electricity by using the charged fission fragments. The first theoretical treatment of direct energy conversion (DEC) appeared in the literature in 1957. Experiments were conducted over the next ten years, which identified a number of problem areas. Research declined by the late 1960's due to technical challenges that limited performance. Under the Nuclear Energy Research Initiative the authors are determining if these technical challenges can be overcome with todays technology. The authors present the basic principles of DEC reactors, review previous research, discuss problem areas in detail, and identify technological developments of the last 30 years that can overcome these obstacles. As an example, the fission electric cell must be insulated to avoid electrons crossing the cell. This insulation could be provided by a magnetic field as attempted in the early experiments. However, from work on magnetically insulated ion diodes they know how to significantly improve the field geometry. Finally, a prognosis for future development of DEC reactors will be presented

  9. Notes on Women Who Rock: Making Scenes, Building Communities: Participatory Research, Community Engagement, and Archival Practice

    Directory of Open Access Journals (Sweden)

    Michelle Habell-Pallán

    2014-07-01

    Full Text Available Since 2011, Women Who Rock (WWR has brought together scholars, archivists, musicians, media-makers, performers, artists, and activists to explore the role of women and popular music in the creation of cultural scenes and social justice movements in the Americas and beyond. The project promotes generative dialogue and documentation by “encompassing several interwoven components: project-based coursework at the graduate and undergraduate levels; an annual participant-driven conference and film festival; and an oral history archive hosted by the University of Washington Libraries Digital Initiatives Program that ties the various components together” (Bartha 8. In our courses, programming, and archive, we examine the politics of performance, social identity, and material access in music scenes, cultures, and industries. Performance studies scholar Daphne Brooks argues that the “confluence of cultural studies, rock studies, and third wave feminist critical studies makes it possible now more than ever to continue to critique and re-interrogate the form and content of popular music histories” (58. WWR implements this approach, asking how particular stories of popular music determine a performer, band, or scene’s “legendary” status or excision from the official annals of memory. WWR reshapes conventional understandings of popular music studies by initiating collective methods of participatory research, as well as community collaboration and dialogue. By way of WWR, we seek to transform traditional models of popular music studies, instigating new convergences between academic disciplines and critical approaches that create alternative histories and new forms of knowledge.

  10. Internet accessible hot cell with gamma spectroscopy at the Missouri S and T nuclear reactor

    International Nuclear Information System (INIS)

    Grant, Edwin; Mueller, Gary; Castano, Carlos; Usman, Shoaib; Kumar, Arvind

    2011-01-01

    Highlights: → A dual-chambered internet-accessible heavily shielded facility has been built. → The facility allows distance users to analyze neutron irradiated samples remotely. → The Missouri S and T system uses computer automation with user feedback. → The system can analyze multiple samples and assist several researchers concurrently. - Abstract: A dual-chambered internet-accessible heavily shielded facility with pneumatic access to the University of Missouri Science and Technology (Missouri S and T) 200 kW Research Nuclear Reactor (MSTR) core has been built and is currently available for irradiation and analysis of samples. The facility allows authorized distance users engaged in collaborative activities with Missouri S and T to remotely manipulate and analyze neutron irradiated samples. The system consists of two shielded compartments, one for multiple sample storage, and the other dedicated exclusively for radiation measurements and spectroscopy. The second chamber has multiple detector ports, with graded shielding, and has the capability to support gamma spectroscopy using radiation detectors such as an HPGe detector. Both these chambers are connected though a rapid pneumatic system with access to the MSTR nuclear reactor core. This new internet-based system complements the MSTR's current bare pneumatic tube (BPT) and cadmium lined pneumatic tube (CPT) facilities. The total transportation time between the core and the hot cell, for samples weighing 10 g, irradiated in the MSTR core, is roughly 3.0 s. This work was funded by the DOE grant number DE-FG07-07ID14852 and expands the capabilities of teaching and research at the MSTR. It allows individuals who do not have on-site access to a nuclear reactor facility to remotely participate in research and educational activities.

  11. Estudio de un reactor catalítico para la obtención de gas de síntesis

    OpenAIRE

    Romero Sayago, Sara Isabel

    2016-01-01

    Este trabajo se centra en el estudio del proceso de reformado de gas natural con vapor de agua para producir gas de síntesis. Un compuesto, que como su nombre indica, es de gran importancia en la síntesis de muchos productos. En concreto, se estudia el reactor heterogéneo catalítico donde tiene lugar la reacción de reformado. Mediante un programa de simulación de procesos químicos, se optimiza el proceso de reformado para obtener un rendimiento elevado en el reactor con el mínimo consumo e...

  12. The U.S. reduced enrichment research and test reactor (RERTR) program

    International Nuclear Information System (INIS)

    Travelli, A.

    1993-01-01

    Research and test reactors are widely deployed to study the irradiation behavior of materials of interest in nuclear engineering, to produce radioisotopes for medicine, industry, and agriculture, and as a basic research and teaching tool. In order to maximize neutron flux per unit power and/or to minimize capital costs and fuel cycle costs, most of these reactors were de- signed to utilize uranium with very high enrichment (in the 70% to 95% range). Research reactor fuels with such high uranium enrichment cause a potential risk of nuclear weapons proliferation. Over 140 research and test reactors of significant power (between 10 kW and 250 MW) are in operation with very highly enriched uranium in more than 35 countries, with total power in excess of 1,700 MW. The overall annual fuel requirement of these reactors corresponds to approximately 1,200 kg of 235 U. This highly strategic material is normally exported from the United States, converted to metal form, shipped to a fuel fabricator, and then shipped to the reactor site in finished fuel element form. At the reactor site the fuel is first stored, then irradiated, stored again, and eventually shipped back to the United States for reprocessing. The whole cycle takes approximately four years to complete, bringing the total required fuel inventory to approximately 5,000 kg of 235 U. The resulting international trade in highly-enriched uranium may involve several countries in the process of refueling a single reactor and creates a considerable concern that the highly-enriched uranium may be diverted for non-peaceful purposes while in fabrication, transport, or storage, particularly when it is in the unirradiated form. The proliferation resistance of nuclear fuels used in research and test reactors can be considerably improved by reducing their uranium enrichment to a value less than 20%, but significantly greater than natural to avoid excessive plutonium production

  13. Assessment of groundwater quality using geographical information system (GIS), at north-east Cairo, Egypt.

    Science.gov (United States)

    El-Shahat, M F; Sadek, M A; Mostafa, W M; Hagagg, K H

    2016-04-01

    The present investigation has been conducted to delineate the hydrogeochemical and environmental factors that control the water quality of the groundwater resources in the north-east of Cairo. A complementary approach based on hydrogeochemistry and a geographical information system (GIS) based protectability index has been employed for conducting this work. The results from the chemical analysis revealed that the groundwater of the Quaternary aquifer is less saline than that of the Miocene aquifer and the main factors that control the groundwater salinity in the studied area are primarily related to the genesis of the original recharging water modified after by leaching, dissolution, cation exchange, and fertilizer leachate. The computed groundwater quality index (WQI) falls into two categories: fair for almost all the Miocene groundwater samples, while the Quaternary groundwater samples are all have a good quality. The retarded flow and non-replenishment of the Miocene aquifer compared to the renewable active recharge of the Quaternary aquifer can explain this variation of WQI. The index and overlay approach exemplified by the DUPIT index has been used to investigate the protectability of the study aquifers against diffuse pollutants. Three categories (highly protectable less vulnerable, moderately protectable moderately vulnerable and less protectable highly vulnerable) have been determined and areally mapped.

  14. Reactor container

    International Nuclear Information System (INIS)

    Kojima, Yoshihiro; Hosomi, Kenji; Otonari, Jun-ichiro.

    1997-01-01

    In the present invention, a catalyst for oxidizing hydrogen to be disposed in a reactor container upon rupture of pipelines of a reactor primary coolant system is prevented from deposition of water droplets formed from a reactor container spray to suppress elevation of hydrogen concentration in the reactor container. Namely, a catalytic combustion gas concentration control system comprises a catalyst for oxidizing hydrogen and a support thereof. In addition, there is also disposed a water droplet deposition-preventing means for preventing deposition of water droplets in a reactor pressure vessel on the catalyst. Then, the effect of the catalyst upon catalytic oxidation reaction of hydrogen can be kept high. The local elevation of hydrogen concentration can be prevented even upon occurrence of such a phenomenon that various kinds of mobile forces in the container such as dry well cooling system are lost. (I.S.)

  15. Activity on non-destructive testing as constituent element of the quality management in accordance with ISO 9001:2000 standard at The Institute of Nuclear Physics, Kazakhstan

    International Nuclear Information System (INIS)

    Kadyrzhanov, K.K.; Kislitsin, S.B.; Ablanov, M.B.

    2004-01-01

    An increase of technical and public safety requirements for facilities of nuclear industries, an efficient quality control based on non-destructive testing (NDT) techniques is crucial. Therefore, Institute of Nuclear Physics (INP) through NDT Division makes efforts towards a competent NDT inspection of its facilities starting from research reactor of WWR-K type with a further activity according to the National Program for Development in Nuclear Industry. The additional objective is to harmonize the present codes and standards for Nuclear Industry as an integral part of the INP policy in a quality management according ISO 9001:2000 Standard. (author)

  16. U.S. progress in the development of very high density low enrichment research reactor fuels

    International Nuclear Information System (INIS)

    Meyer, M. K.; Wachs, D. M.; Jue, J.-F.; Keiser, D. D.; Gan, J.; Rice, F.; Robinson, A.; Woolstenhulme, N. E.; Medvedev, P.; Hofman, G. L.; Kim, Y.-S.

    2012-01-01

    The effort to develop low-enriched fuels for high power research reactors began world-wide in 1996. Since that time, hundreds of fuel specimens have been tested to investigate the operational limits of many variations of U-Mo alloy dispersion and monolithic fuels. In the U.S., the fuel development program has focused on the development of monolithic fuel, and is currently transitioning from conducting research experiments to the demonstration of large scale, prototypic element assemblies. These larger scale, integral fuel performance demonstrations include the AFIP-7 test of full-sized, curved plates configured as an element, the RERTR-FE irradiation of hybrid fuel elements in the Advanced Test Reactor, reactor specific Design Demonstration Experiments, and a multi-element Base Fuel Demonstration. These tests are conducted alongside mini-plate tests designed to prove fuel stability over a wide range of operating conditions. Along with irradiation testing, work on collecting data on fuel plate mechanical integrity, thermal conductivity, fission product release, and microstructural stability is underway. (authors)

  17. Power Trip Set-points of Reactor Protection System for New Research Reactor

    International Nuclear Information System (INIS)

    Lee, Byeonghee; Yang, Soohyung

    2013-01-01

    This paper deals with the trip set-point related to the reactor power considering the reactivity induced accident (RIA) of new research reactor. The possible scenarios of reactivity induced accidents were simulated and the effects of trip set-point on the critical heat flux ratio (CHFR) were calculated. The proper trip set-points which meet the acceptance criterion and guarantee sufficient margins from normal operation were then determined. The three different trip set-points related to the reactor power are determined based on the RIA of new research reactor during FP condition, over 0.1%FP and under 0.1%FP. Under various reactivity insertion rates, the CHFR are calculated and checked whether they meet the acceptance criterion. For RIA at FP condition, the acceptance criterion can be satisfied even if high power set-point is only used for reactor trip. Since the design of the reactor is still progressing and need a safety margin for possible design changes, 18 MW is recommended as a high power set-point. For RIA at 0.1%FP, high power setpoint of 18 MW and high log rate of 10%pp/s works well and acceptance criterion is satisfied. For under 0.1% FP operations, the application of high log rate is necessary for satisfying the acceptance criterion. Considering possible decrease of CHFR margin due to design changes, the high log rate is suggested to be 8%pp/s. Suggested trip set-points have been identified based on preliminary design data for new research reactor; therefore, these trip set-points will be re-established by considering design progress of the reactor. The reactor protection system (RPS) of new research reactor is designed for safe shutdown of the reactor and preventing the release of radioactive material to environment. The trip set point of RPS is essential for reactor safety, therefore should be determined to mitigate the consequences from accidents. At the same time, the trip set-point should secure margins from normal operational condition to avoid

  18. Tank type reactor

    International Nuclear Information System (INIS)

    Otsuka, Fumio.

    1989-01-01

    The present invention concerns a tank type reactor capable of securing reactor core integrity by preventing incorporation of gases to an intermediate heat exchanger, thgereby improving the reliability. In a conventional tank type reactor, since vortex flows are easily caused near the inlet of an intermediate heat exchanger, there is a fear that cover gases are involved into the coolant main streams to induce fetal accidents. In the present invention, a reactor core is suspended by way of a suspending body to the inside of a reactor vessel and an intermediate heat exchanger and a pump are disposed between the suspending body and the reactor vessel, in which a vortex current preventive plate is attached at the outside near the coolant inlet on the primary circuit of the intermediate heat exchanger. In this way vortex or turbulence near the inlet of the intermediate heata exchanger or near the surface of coolants can be prevented. Accordingly, the cover gases are no more involved, to insure the reactor core integrity and obtain a tank type nuclear reactor of high reliability. (I.S.)

  19. Advanced reactor development: The LMR integral fast reactor program at Argonne

    International Nuclear Information System (INIS)

    Till, C.E.

    1990-01-01

    Reactor technology for the 21st Century must develop with characteristics that can now be seen to be important for the future, quite different from the things when the fundamental materials and design choices for present reactors were made in the 1950s. Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 3 figs

  20. A Compilation of Boiling Water Reactor Operational Experience for the United Kingdom's Office for Nuclear Regulation's Advanced Boiling Water Reactor Generic Design Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Wheeler, Timothy A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Liao, Huafei [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-12-01

    United States nuclear power plant Licensee Event Reports (LERs), submitted to the United States Nuclear Regulatory Commission (NRC) under law as required by 10 CFR 50.72 and 50.73 were evaluated for reliance to the United Kingdom’s Health and Safety Executive – Office for Nuclear Regulation’s (ONR) general design assessment of the Advanced Boiling Water Reactor (ABWR) design. An NRC compendium of LERs, compiled by Idaho National Laboratory over the time period January 1, 2000 through March 31, 2014, were sorted by BWR safety system and sorted into two categories: those events leading to a SCRAM, and those events which constituted a safety system failure. The LERs were then evaluated as to the relevance of the operational experience to the ABWR design.

  1. Inspection program for U.S. research reactors

    International Nuclear Information System (INIS)

    Isaac, Patrick J.

    2010-01-01

    This paper presents an established program for inspection of nuclear research reactors to ensure that systems and techniques are in accordance with regulatory requirements and to provide protection for the health and safety of the public. The inspection program, implemented from the time a facility gets licensed, remains in effect through operations, shutdown, decommissioning, and until the license is terminated. The program establishes inspection methodology for operating, safeguards, and decommissioning activities. Using a performance- based approach, inspectors focus their attention on activities important to safety. Inspection procedures allow the inspectors to assess facility safety and compliance to applicable requirements. A well designed inspection program is an integral part of the mechanism to ensure that the level of performance in the strategic areas of reactor safety, radiation safety, and safeguards is acceptable and provides adequate protection of public health and safety. (author)

  2. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

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

  3. Psychopathological effects of the Colombian armed conflict in families forcibly displaced resettled in the municipality of Cairo in 2008

    Directory of Open Access Journals (Sweden)

    José Alonso Andrade Salazar

    2011-11-01

    Full Text Available This paper aims to establish the mental health conditions prevalent in 20 displaced persons (36 families resettled in the Municipality of Cairo - Valley in 2008, for it is used, self-applied scale for measuring the Zung Depression and Conde The mood disorder questionnaire (MDQ, and Davidson Trauma Scale (DTS which makes the symptoms of posttraumatic stress disorder (PTSD.  The results showed the presence of mild depression (20%, moderate (60%“higher in women”, and major depression (30%, with a gender relationship in 2 women for every man. It was found that 100% of the population has indicators PTSD, with extreme gravity of 50% and 40% moderate.Regarding the 30% Bipolar disorder was not the case, a possible case and 65%, 5% cases. The data indicate that the psychological impact of conflict persist in  populations "especially women", becoming even comorbid psychopathology decrease insecure environment.

  4. Planning the Decommissioning of Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Podlaha, J., E-mail: pod@ujv.cz [Nuclear Research Institute Rez, 25068 Rez (Czech Republic)

    2013-08-15

    In the Czech Republic, three research nuclear reactors are in operation. According to the valid legislation, preliminary decommissioning plans have been prepared for all research reactors in the Czech Republic. The decommissioning plans shall be updated at least every 5 years. Decommissioning funds have been established and financial resources are regularly deposited. Current situation in planning of decommissioning of research reactors in the Czech Republic, especially planning of decommissioning of the LVR-15 research reactor is described in this paper. There appeared new circumstances having wide impact on the decommissioning planning of the LVR-15 research reactor: (1) Shipment of spent fuel to the Russian Federation for reprocessing and (2) preparation of processing of radioactive waste from reconstruction of the VVR-S research reactor (now LVR-15 research reactor). The experience from spent fuel shipment to the Russian Federation and from the process of radiological characterization and processing of radioactive waste from reconstruction of the VVR-S research reactor (now the LVR-15 research reactor) and the impact on the decommissioning planning is described in this paper. (author)

  5. Postirradiation thermocyclic loading of ferritic-martensitic structural materials

    Science.gov (United States)

    Belyaeva, L.; Orychtchenko, A.; Petersen, C.; Rybin, V.

    Thermonuclear fusion reactors of the Tokamak-type will be unique power engineering plants to operate in thermocyclic mode only. Ferritic-martensitic stainless steels are prime candidate structural materials for test blankets of the ITER fusion reactor. Beyond the radiation damage, thermomechanical cyclic loading is considered as the most detrimental lifetime limiting phenomenon for the above structure. With a Russian and a German facility for thermal fatigue testing of neutron irradiated materials a cooperation has been undertaken. Ampule devices to irradiate specimens for postirradiation thermal fatigue tests have been developed by the Russian partner. The irradiation of these ampule devices loaded with specimens of ferritic-martensitic steels, like the European MANET-II, the Russian 05K12N2M and the Japanese Low Activation Material F82H-mod, in a WWR-M-type reactor just started. A description of the irradiation facility, the qualification of the ampule device and the modification of the German thermal fatigue facility will be presented.

  6. Design, fabrication and transportation of Si rotating device

    International Nuclear Information System (INIS)

    Kimura, Nobuaki; Imaizumi, Tomomi; Takemoto, Noriyuki; Tanimoto, Masataka; Saito, Takashi; Hori, Naohiko; Tsuchiya, Kunihiko; Romanova, Nataliya; Gizatulin, Shamil; Martyushov, Alexandr; Nakipov, Darkhan; Chakrov, Petr; Tanaka, Futoshi; Nakajima, Takeshi

    2012-06-01

    Si semiconductor production by Neutron Transmutation Doping (NTD) method using the Japan Materials Testing Reactor (JMTR) has been investigated in Neutron Irradiation and Testing Reactor Center, Japan Atomic Energy Agency (JAEA) in order to expand industry use. As a part of investigations, irradiation test of silicon ingot for development of NTD-Si with high quality was planned using WWR-K in Institute of Nuclear Physics (INP), National Nuclear Center of Republic of Kazakhstan (NNC-RK) based on one of specific topics of cooperation (STC), Irradiation Technology for NTD-Si (STC No.II-4), on the implementing arrangement between NNC-RK and the JAEA for 'Nuclear Technology on Testing/Research Reactors' in cooperation in research and development in nuclear energy and technology. As for the irradiation test, Si rotating device was fabricated in JAEA, and the fabricated device was transported with irradiation specimens from JAEA to INP-NNC-RK. This report described the design, the fabrication, the performance test of the Si rotating device and transportation procedures. (author)

  7. Revised reactor accident source terms in the U.S. and implementation for light water reactors

    International Nuclear Information System (INIS)

    Soffer, L.; Lee, J.Y.

    1992-01-01

    Current NRC reactor accident source terms used for licensing are contained in Regulatory Guides 1.3 and 1.4 and specify that 100 % of the core inventory of noble gases and 25 % of the iodine fission products are assumed to be instantaneously available for release from the containment. The chemical form of the iodine fission products is also assumed to be predominantly elemental (I 2 ) iodine. These assumptions have strongly affected present nuclear plant designs. Severe accident research results have confirmed that although the current source term is very substantial and has resulted in a very high level of plant capability, the present source term is no longer compatible with a realistic understanding of severe accidents. The NRC has issued a proposed revision of the reactor accident source terms as part of several regulatory activities to incorporate severe accident insights for future plants. A revision to 10 CFR 100 is also being proposed to specify site criteria directly and to eliminate source terms and doses for site evaluation. Reactor source terms will continue to be important in evaluating plant designs. Although intended primarily for future plants, existing and evolutionary power plants may voluntarily apply revised accident source term insights as well in licensing. The proposed revised accident source terms are presented in terms of fission product composition, magnitude, timing and iodine chemical form. Some implications for light water reactors are discussed. (author)

  8. An overview of the U.S. Department of Energy Experimental Boiling Water Reactor Decontamination and Decommissioning Project

    International Nuclear Information System (INIS)

    Murphie, W.E.; Mckernan, M.L.

    1991-01-01

    This paper provides an overview of the U.S. Department of Energy's (DOE) Experimental Boiling Water Reactor (EBWR) Decontamination and Decommissioning (D and D) Project. Physical decommissioning work started in 1986 and is scheduled for completion in 1994. The project total estimated cost is 14.3 million (1990, U.S.) dollars. The reactor pressure vessel will be removed by segmentation. Another notable project feature is that D and D operations were planned for and carried out with a small work force comprised of four to six D and D laborers, one or two health physics technicians, an engineer, and a project manager. When the D and D work is completed the facility will be recycled for other productive uses. (author)

  9. Use of enriched uranium in Canada's power reactors

    International Nuclear Information System (INIS)

    Dormuth, K.W.; Jackson, D.P.

    2011-01-01

    Recent trends in Canadian nuclear power reactor design and proposed development of nuclear power in Canada have indicated the possibility that Canada will break with its tradition of natural uranium fuelled systems, designed for superior neutron economy and, hence, superior uranium utilization. For instance, the Darlington B new reactor project procurement process included three reactor designs, all employing enriched fuel, although a natural uranium reactor design was included at a late stage in the ensuing environmental assessment for the project as an alternative technology. An evaluation of the alternative designs should include an assessment of the environmental implications through the entire fuel cycle, which unfortunately is not required by the environmental assessment process. Examples of comparative environmental implications of the reactor designs throughout the fuel cycle indicate the importance of these considerations when making a design selection. As Canada does not have enrichment capability, a move toward the use of enriched fuel would mean that Canada would be exporting natural uranium and buying back enriched uranium with value added. From a waste management perspective, Canada would need to deal with mill, refinery, and conversion tailings, as well as with the used fuel from its own reactors, while the enrichment supplier would retain depleted uranium with some commercial value. On the basis of reasoned estimates based on publicly available information, it is expected that enrichment in Canada is likely to be more profitable than exporting natural uranium and buying back enriched uranium. Further, on the basis of environmental assessments for enrichment facilities in other countries, it is expected that an environmental assessment of a properly sited enrichment facility would result in approval. (author)

  10. Advanced CANDU reactors

    International Nuclear Information System (INIS)

    Dunn, J.T.; Finlay, R.B.; Olmstead, R.A.

    1988-12-01

    AECL has undertaken the design and development of a series of advanced CANDU reactors in the 700-1150 MW(e) size range. These advanced reactor designs are the product of ongoing generic research and development programs on CANDU technology and design studies for advanced CANDU reactors. The prime objective is to create a series of advanced CANDU reactors which are cost competitive with coal-fired plants in the market for large electricity generating stations. Specific plant designs in the advanced CANDU series will be ready for project commitment in the early 1990s and will be capable of further development to remain competitive well into the next century

  11. K-East and K-West Reactors

    Data.gov (United States)

    Federal Laboratory Consortium — Hanford's "sister reactors", the K-East and the K-West Reactors, were built side-by-side in the early 1950's. The two reactors went operational within four months of...

  12. Reactor pressure tank

    International Nuclear Information System (INIS)

    Dorner, H.; Scholz, M.; Jungmann, A.

    1975-01-01

    In a reactor pressure tank for a nuclear reactor, self-locking hooks engage a steel ring disposed over the removable cover of the steel vessel. The hooks exert force upon the cover to maintain the cover in a closed position during operation of the reactor pressure tank. The force upon the removal cover is partly the result of the increasing temperature and thermal expansion of the steel vessel during operation. The steel vessel is surrounded by a reinforced-concrete tank. (U.S.)

  13. Application of S-CO{sub 2} Cycle for Small Modular Reactor coupled with Desalination System

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Won Woong; Bae, Seong Jun; Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of)

    2016-10-15

    The Korean small modular reactor, SMART (System-integrated Modular Advanced ReacTor, 100MWe), is designed to achieve enhanced safety and improved economics through reliable passive safety systems, a system simplification and component modularization. SMART can generate electricity and provide water by seawater desalination. However, due to the desalination aspect of SMART, the total amount of net electricity generation is decreased from 100MWe to 90MWe. The authors suggest in this presentation that the reduction of electricity generation can be replenished by applying S-CO{sub 2} power cycle technology. The S-CO{sub 2} Brayton cycle, which is recently receiving significant attention as the next generation power conversion system, has some benefits such as high cycle efficiency, simple configuration, compactness and so on. In this study, the cycle performance analysis of the S-CO{sub 2} cycles for SMART with desalination system is conducted. The simple recuperated S-CO{sub 2} cycle is revised for coupling with desalination system. The three revised layout are proposed for the cycle performance comparison. In this results of the 3rd revised layout, the cycle efficiency reached 37.8%, which is higher than the efficiency of current SMART with the conventional power conversion system 30%.

  14. Status Report on Scoping Reactor Physics and Sensitivity/Uncertainty Analysis of LR-0 Reactor Molten Salt Experiments

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Mueller, Donald E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Patton, Bruce W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division; Powers, Jeffrey J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Reactor and Nuclear Systems Division

    2016-08-31

    Experiments are being planned at Research Centre Rež (RC Rež) to use the FLiBe (2 7LiF-BeF2) salt from the Molten Salt Reactor Experiment (MSRE) to perform reactor physics measurements in the LR-0 low power nuclear reactor. These experiments are intended to inform on neutron spectral effects and nuclear data uncertainties for advanced reactor systems utilizing FLiBe salt in a thermal neutron energy spectrum. Oak Ridge National Laboratory (ORNL) is performing sensitivity/uncertainty (S/U) analysis of these planned experiments as part of the ongoing collaboration between the United States and the Czech Republic on civilian nuclear energy research and development. The objective of these analyses is to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a status update on the S/U analyses of critical experiments at the LR-0 Reactor relevant to fluoride salt-cooled high temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts. The S/U analyses will be used to inform design of FLiBe-based experiments using the salt from MSRE.

  15. Status Report on Scoping Reactor Physics and Sensitivity/Uncertainty Analysis of LR-0 Reactor Molten Salt Experiments

    International Nuclear Information System (INIS)

    Brown, Nicholas R.; Mueller, Donald E.; Patton, Bruce W.; Powers, Jeffrey J.

    2016-01-01

    Experiments are being planned at Research Centre Rež (RC Rež) to use the FLiBe (2 "7LiF-BeF_2) salt from the Molten Salt Reactor Experiment (MSRE) to perform reactor physics measurements in the LR-0 low power nuclear reactor. These experiments are intended to inform on neutron spectral effects and nuclear data uncertainties for advanced reactor systems utilizing FLiBe salt in a thermal neutron energy spectrum. Oak Ridge National Laboratory (ORNL) is performing sensitivity/uncertainty (S/U) analysis of these planned experiments as part of the ongoing collaboration between the United States and the Czech Republic on civilian nuclear energy research and development. The objective of these analyses is to produce the sensitivity of neutron multiplication to cross section data on an energy-dependent basis for specific nuclides. This report provides a status update on the S/U analyses of critical experiments at the LR-0 Reactor relevant to fluoride salt-cooled high temperature reactor (FHR) and liquid-fueled molten salt reactor (MSR) concepts. The S/U analyses will be used to inform design of FLiBe-based experiments using the salt from MSRE.

  16. Luncheon address: Development of the CANDU reactor

    International Nuclear Information System (INIS)

    Bain, A.S.

    1997-01-01

    The paper is a highlight of the some of the achievements in the development of the CANDU Reactor, taken from the book C anada Enters the Nuclear Age . The CANDU reactor is one of Canada's greatest scientific/engineering achievements, that started in the 1940's and bore fruit with the reactors of the 60's, 70's, and 80's. The Government decided in the 1950's to proceed with a demonstration nuclear power reactor (NPD), AECL invited 7 Canadian corporations to bid on a contract to design and construct the NPD plant. General Electric was selected. A utility was also essential for participation and Ontario Hydro was chosen. In May 1957 it was concluded that the minimum commercial size would be about 200MWe and it should use horizontal pressure tubes to contain the fuel and pressurized heavy water coolant. The book also talks of standard out-reactor components such as pumps, valves, steam generators and piping. A major in-reactor component of interest was the fuel, fuel channels and pressure tubes. A very high level of cooperation was required for the success of the CANDU program

  17. Reactor feedwater system

    International Nuclear Information System (INIS)

    Kagaya, Hiroyuki; Tominaga, Kenji.

    1993-01-01

    In a simplified water type reactor using a gravitationally dropping emergency core cooling system (ECCS), the present invention effectively prevents remaining high temperature water in feedwater pipelines from flowing into the reactor upon occurrence of abnormal events. That is, (1) upon LOCA, if a feedwater pipeline injection valve is closed, boiling under reduced pressure of the remaining high temperature water occurs in the feedwater pipelines, generated steams prevent the remaining high temperature water from flowing into the reactor. Accordingly, the reactor is depressurized rapidly. (2) The feedwater pipeline injection valve is closed and a bypassing valve is opened. Steams generated by boiling under reduced pressure of the remaining high temperature water in the feedwater pipelines are released to a condensator or a suppression pool passing through bypass pipelines. As a result, the remaining high temperature water is prevented from flowing into the reactor. Accordingly, the reactor is rapidly depressurized and cooled. It is possible to accelerate the depressurization of the reactor by the method described above. Further, load on the depressurization valve disposed to a main steam pipe can be reduced. (I.S.)

  18. German research reactor back-end provisions

    International Nuclear Information System (INIS)

    Koester, Siegfried; Gruber, Gerhard

    2002-01-01

    Germany has several types of Research Reactors in operation. These reactors use fuel containing uranium of U.S. origin. Basically all the fuel which will be spent until May 2006 will be returned to the U.S. under existing contracts with the U.S. Department of Energy. The contracts are based on the U.S. FRR SNF (Foreign Research Reactor Spent Nuclear Fuel) Program which started in May 1996 and which will last for 10 years. In 1990, the German Federal Government started a program to long-term store (approx. 40 years) and finally dispose of spent fuel in Germany after the so-called U.S. fuel return window will be closed. In order to long-term store the fuel, a special container was designed which covers all different types of spent fuel from the Research Reactors. The container called 'CASTOR MTR 2' is basically licensed and is already in use for the spent fuel of Russian origin from the 'Research Reactor Rossendorf' in the eastern part of Germany. All that fuel is expected to be stored in the existing intermediate storage facility, the so-called BZA (Brennelemente Zwischenlager Ahaus). BZA already accomodates spent fuel from the former THTR-300 high temperature reactor. A final repository does not yet exist in Germany. Alternative provisions to close the back-end of the Research Reactor fuel cycle are reprocessing at COGEMA (France) or in Russian facilities, perspectively. Waste return in a form to be agreed will be mandatory, at least in France. (author)

  19. Secondhand smoke in waterpipe tobacco venues in Istanbul, Moscow, and Cairo.

    Science.gov (United States)

    Moon, Katherine A; Magid, Hoda; Torrey, Christine; Rule, Ana M; Ferguson, Jacqueline; Susan, Jolie; Sun, Zhuolu; Abubaker, Salahaddin; Levshin, Vladimir; Çarkoğlu, Aslı; Radwan, Ghada Nasr; El-Rabbat, Maha; Cohen, Joanna; Strickland, Paul; Navas-Acien, Ana; Breysse, Patrick N

    2015-10-01

    The prevalence of waterpipe tobacco smoking has risen in recent decades. Controlled studies suggest that waterpipe secondhand smoke (SHS) contains similar or greater quantities of toxicants than cigarette SHS, which causes significant morbidity and mortality. Few studies have examined SHS from waterpipe tobacco in real-world settings. The purpose of this study was to quantify SHS exposure levels and describe the characteristics of waterpipe tobacco venues. In 2012-2014, we conducted cross-sectional surveys of 46 waterpipe tobacco venues (9 in Istanbul, 17 in Moscow, and 20 in Cairo). We administered venue questionnaires, conducted venue observations, and sampled indoor air particulate matter (PM2.5) (N=35), carbon monoxide (CO) (N=23), particle-bound polycyclic aromatic hydrocarbons (p-PAHs) (N=31), 4-methylnitrosamino)-1-(3-pyridyl)-1-butanone (NNK) (N=43), and air nicotine (N=46). Venue characteristics and SHS concentrations were highly variable within and between cities. Overall, we observed a mean (standard deviation (SD)) of 5 (5) waterpipe smokers and 5 (3) cigarette smokers per venue. The overall median (25th percentile, 75th percentile) of venue mean air concentrations was 136 (82, 213) µg/m(3) for PM2.5, 3.9 (1.7, 22) ppm for CO, 68 (33, 121) ng/m(3) for p-PAHs, 1.0 (0.5, 1.9) ng/m(3) for NNK, and 5.3 (0.7, 14) µg/m(3) for nicotine. PM2.5, CO, and p-PAHs concentrations were generally higher in venues with more waterpipe smokers and cigarette smokers, although associations were not statistically significant. High concentrations of SHS constituents known to cause health effects indicate that indoor air quality in waterpipe tobacco venues may adversely affect the health of employees and customers. Copyright © 2015 Elsevier Inc. All rights reserved.

  20. Research reactor safety - an overview of crucial aspects

    Energy Technology Data Exchange (ETDEWEB)

    Laverie, M. [Atomic Energy Commission, Saclay, F-91191 Gif sur Yvette (France)

    1998-07-01

    Chronology of the commissioning orders of the French research reactors illustrates the importance of the time factor. When looking at older reactors, one must, on one hand, demonstrate, not only the absence of risks tied to the reactor's ageing, but, on the other hand, adapt the reactor's original technical designs to today's safety practices and standards. The evolution of reactor safety requirements over the last twenty years sometimes makes this adaptation difficult. The design of the next research reactors, after a one to two decades pause in construction, will require to set up new safety assessment bases that will have to take into account the nuclear power plant safety evolution. As a general statement, research reactor safety approaches will require the incorporation of specific design rules for research reactors: experience feedback for one of a kind design, frequent modifications required by research programmes, special operational requirements with operators/researchers interfaces. (author)

  1. Meeting the reactor operator's information needs using functional analysis

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, W.R.; Clark, M.T.

    1980-01-01

    Since the accident at Three Mile Island, many ideas have been proposed for assisting the reactor operator during emergency situations. However, some of the suggested remedies do not alleviate an important shortcoming of the TMI control room: the operators were not presented with the information they needed in a manner which would allow prompt diagnosis of the problem. To address this problem, functional analysis is being applied at the LOFT facility to ensure that the operator's information needs are being met in his procedures and graphic displays. This paper summarizes the current applications of functional analysis at LOFT.

  2. The nuclear question at the start of the '80s: the breeder reactor

    International Nuclear Information System (INIS)

    Owen, R.; Svensson, B.

    1980-01-01

    The four newspaper articles and the letter cover the following matters: general introduction about breeder reactors and the situation in Swedish politics; visit to Dounreay to discuss breeder reactors (breeding, safety, plutonium production, radiation protection); PuO 2 -UO 2 mixed fuel; description of breeder reactors; efficiency in use of U-235; DFR and PFR; breeder reactors in Swedish politics (arguments for and against nuclear power in general, breeder reactors in particular); discussion of the future of nuclear power in Sweden. (U.K.)

  3. 78 FR 71675 - Update of the Office of Nuclear Reactor Regulation's Electronic Operating Reactor Correspondence

    Science.gov (United States)

    2013-11-29

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0260] Update of the Office of Nuclear Reactor Regulation's Electronic Operating Reactor Correspondence The U.S. Nuclear Regulatory Commission (NRC) is issuing this Federal Register notice to inform the public of a slight change in the manner of distribution of publicly available operating reactor licensing...

  4. Design and construction of a preamplifier for research reactor control system using Russia’s neutron detectors

    International Nuclear Information System (INIS)

    Trinh Dinh Hai; Vo Van Tai; Le Van Diep; Nguyen Nhi Dien

    2016-01-01

    This paper presents the design and construction of a preamplifier device for Research Reactor Control System, using Russia’s Neutron Detectors of ionization and fission chambers. In this work, the preamplifier device which consists of a wide range Current to Frequency Converter block used with a compensation ionization chamber type KNK-3 to measure the thermal neutron flux in the range of 1x10"6 - 1x10"1"1 n/cm"2.s, a Pulse Preamplifier block used with a fission chamber type KNK-15 to measure the thermal neutron flux in the range of 1x10"0 - 1x10"6 n/cm"2.s, and a Power Supply block, was designed and tested in different conditions in the laboratory and at Dalat Nuclear Research Reactor (DNRR). Obtained results show that, the above blocks have almost design specifications as equivalent or better in comparison with the same function blocks of the DNRR Control System which were designed by the former Soviet Union. They also meet the utilization requirements as well as the experimental and training purposes. (author)

  5. Fusion Reactor Materials

    Energy Technology Data Exchange (ETDEWEB)

    Decreton, M

    2002-04-01

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed.

  6. Nuclear Power: Outlook for New U.S. Reactors

    National Research Council Canada - National Science Library

    Parker, Larry; Holt, Mark

    2007-01-01

    .... The renewed interest in nuclear power has resulted primarily from higher prices for natural gas, improved operation of existing reactors, and uncertainty about future restrictions on coal emissions...

  7. Reactor power measuring device

    International Nuclear Information System (INIS)

    Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

    1993-01-01

    The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

  8. SEARCHING FOR URBAN PATTERNS; AN ASSESSMENT OF HISTORIC EDGES AND ITS SURROUNDING CONTEXT: HISTORIC CAIRO AS A CASE STUDY

    Directory of Open Access Journals (Sweden)

    Nabil Mohareb

    2016-07-01

    Full Text Available This paper analyzes the urban edges of historic cities. Managing these edges would enhance the success of any intervention projects inside the historic fabric. The paper develops and tests a method of analytical assessment framework that is applicable for quantitative analysis within an urban edge. It is capable of measuring micro and macro levels of analysis of historic urban edges with reference to their spatial configuration. In addition, the paper searches for repetitive spatial configuration patterns. The main case study is Historic Cairo. The paper reveals that there are apparent patterns of cause and effect of both spatial configurations and related activities along the urban edges, forming different type of barriers. The paper discovers the repetitive spatial, architectural, and land-use patterns that exist on various edges. These patterns enable the possibility of learning and acquiring from other successful interventions that have been applied to similar patterns, without being limited to cultural or contextual differences.

  9. STUDI KOMPARATIF ANTARA UNIVERSAL DECLARATION OF HUMAN RIGHTS 1948 DAN THE CAIRO DECLARATION ON HUMAN RIGHTS IN ISLAM 1990

    Directory of Open Access Journals (Sweden)

    Sunaryo Sunaryo

    2014-03-01

    Full Text Available Diskusi Hak Asasi Manusia (HAM merupakan salah satu topik yang tetap aktual dan mengglobal di samping masalah demokrasi dan lingkungan hidup. Manusia sebagai makhluk Tuhan dan makhluk sosial memiliki hak-hak asasi yang mesti dihormati dan dilindungi oleh siapapun. Di dalam Universal Declaration of Human Rights 1948 (UDHR dan di dalam The Cairo Declaration on Human Rights In Islam 1990 (CD, berbagai macam hak-hak asasi dimaksud telah diatur secara general dan komprehensif. Meskipun demikian, di antara kedua deklarasi tersebut di samping mempunyai persamaan juga memiliki perbedaan. Perbedaan-perbedaan tersebut antara lain tentang asal atau sumber dari masing-masing deklarasi yang tidak sama, hak atas kebebasan beragama dan hak untuk menikah, serta hak atas kewarganegaraan seseorang. Sementara itu ada juga ketentuan-ketentuan yang diatur di dalam CD tetapi tidak diatur dalam UDHR atau sebaliknya, seperti tentang riba (Pasal 14 CD tidak diatur di dalam UDHR, sebaliknya ketentuan tentang kebebasan berserikat dan berkumpul (Pasal 20 UDHR tidak diatur di dalam CD

  10. IAEA Laboratory Activities. The IAEA Laboratories at Vienna and Seibersdorf, the International Laboratory of Marine Radioactivity at Monaco, the International Centre for Theoretical Physics, Trieste, the Middle Eastern Regional Radioisotope Centre for the Arab Countries, Cairo. Fifth Report

    International Nuclear Information System (INIS)

    1968-01-01

    This fifth report describes development and work during the year 1967. It includes activities of the IAEA Laboratories at Vienna and Seibersdorf, the International Laboratory of Marine Radioactivity at Monaco, the International Centre for Theoretical Physics at Trieste, and the Middle Eastern Regional Radioisotope Centre for the Arab Countries at Cairo. Contents: The IAEA Laboratories at Vienna and Seibersdorf: Introduction; Standardization of measurement and of analytical methods related to peaceful applications of nuclear energy; Services to Member States and International Organizations; Chemical and physico-chemical investigations relevant to the Agency's programme; Nuclear techniques in hydrology; Nuclear techniques in medicine; Nuclear techniques in agriculture; Nuclear electronics service and development; Administrative matters. — The International Laboratory of Marine Radioactivity at Monaco: Introduction; Research; Administrative matters. — The International Centre for Theoretical Physics, Trieste: Assistance to developing countries; Research activities; Administrative matters; Annexes. — The Middle Eastern Regional Radioisotope Centre for the Arab Countries, Cairo: Introduction; The scientific programme of the Centre; Publications on work done at the Centre; Finance; Annex. Entirely in English. (author)

  11. Reactor technology

    International Nuclear Information System (INIS)

    Erdoes, P.

    1977-01-01

    This is one of a series of articles discussing aspects of nuclear engineering ranging from a survey of various reactor types for static and mobile use to mention of atomic thermo-electric batteries of atomic thermo-electric batteries for cardiac pacemakers. Various statistics are presented on power generation in Europe and U.S.A. and economics are discussed in some detail. Molten salt reactors and research machines are also described. (G.M.E.)

  12. Advanced Reactor Development in the United States

    Energy Technology Data Exchange (ETDEWEB)

    Giessing, D. F.; Griffith, J. D.; McGoff, D. J.; Rosen, Sol [U. S. Department of Energy, Texas (United States)

    1990-04-15

    In the United States, three technologies are employed for the new generation of advanced reactors. These technologies are Advanced Light Water Reactors (A LWRs) for the 1990s and beyond, the Modular High Temperature Gas Reactor (M HTGR) for commercial use after the turn of the century, and Liquid Metal Reactors (LWRs) to provide energy production and to convert reactor fission waste to a more manageable waste product. Each technology contributes to the energy solution. Light Water Reactors For The 1990s And Beyond--The U. S. Program The economic and national security of the United States requires a diversified energy supply base built primarily upon adequate, domestic resources that are relatively free from international pressures. Nuclear energy is a vital component of this supply and is essential to meet current and future national energy demands. It is a safe, economically continues to contribute to national energy stability, and strength. The Light Water Reactor (LWR) has been a major and successful contributor to the electrical generating needs of many nations throughout the world. It is being counted upon in the United States as a key to revitalizing nuclear energy option in the 1990s. In recent years, DOE joined with the industry to ensure the availability and future viability of the LWR option. This national program has the participation of the Nation's utility industry, the Electric Power Research Institute (EPRI), and several of the major reactor manufacturers and architect-engineers. Separate but coordinated parts of this program are managed by EPRI and DOE.

  13. Nuclear blenders: blended learning from Rensselaer's Reactor Critical Facility

    Energy Technology Data Exchange (ETDEWEB)

    Haley, T.C. [Rensselaer Polytechnic Inst., Troy, NY (United States)

    2011-07-01

    Rensselaer's senior level undergraduate nuclear engineering course 'Critical Reactor Laboratory' is highly regarded and much loved. If you can get in, that is. But now it's a required course, nuclear engineering enrollment is up, and others are knocking on our door to get in. How might one offer such a unique course to the masses, without losing the whole point of a laboratory experience? This presentation looks at the costs and benefits of the transition to a 'blended learning' mode -- the merging of traditional, face-to-face instruction and web-based instruction as a solution. As part of the presentation, the course and the facility will be highlighted by short excepts from the 50 minute movie 'Everything You Always Wanted to Know about Neutron Chain Reactions (but were afraid to ask)'.

  14. IAEA Mission Sees High Commitment to Safety at Ghana's Research Reactor After HEU to LEU Fuel Conversion

    International Nuclear Information System (INIS)

    2018-01-01

    An International Atomic Energy Agency (IAEA) team of experts said the operator of Ghana’s research reactor has demonstrated a high commitment to safety following the conversion of the reactor core to use low enriched uranium (LEU) as fuel instead of high enriched uranium (HEU). The team also made recommendations for further safety enhancements. The Integrated Safety Assessment for Research Reactors (INSARR) team concluded a five-day mission today to assess the safety of the GHARR-1 research reactor, originally commissioned in 1994. The 30 kW reactor, operated by the Ghana Atomic Energy Commission (GAEC) at the National Nuclear Research Institute in the capital Accra, is used primarily for trace element analysis for industrial or agricultural purposes, research, education and training. In 2017, the reactor core was converted in a joint effort by Ghana, the United States and China, with assistance from the IAEA. The IAEA supported the operation to eliminate proliferation risks associated with HEU, while maintaining important scientific research. The team made recommendations for improvements to the GAEC, including: • Completing the revision of reactor safety and operating documents to reflect the results of the commissioning of the reactor after the core fuel conversion. • Enhancing the training and qualification programme for operating personnel. • Improving the capability for monitoring operational safety parameters under all conditions. • Strengthening radiation protection by establishing an effective radiation monitoring of workplace. The GAEC said it will request a follow-up INSARR mission by 2020.

  15. Solid State Reactor Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Mays, G.T.

    2004-03-10

    The Solid State Reactor (SSR) is an advanced reactor concept designed to take advantage of Oak Ridge National Laboratory's (ORNL's) recently developed graphite foam that has enhanced heat transfer characteristics and excellent high-temperature mechanical properties, to provide an inherently safe, self-regulated, source of heat for power and other potential applications. This work was funded by the U.S. Department of Energy's Nuclear Energy Research Initiative (NERI) program (Project No. 99-064) from August 1999 through September 30, 2002. The initial concept of utilizing the graphite foam as a basis for developing an advanced reactor concept envisioned that a suite of reactor configurations and power levels could be developed for several different applications. The initial focus was looking at the reactor as a heat source that was scalable, independent of any heat removal/power conversion process. These applications might include conventional power generation, isotope production and destruction (actinides), and hydrogen production. Having conducted the initial research on the graphite foam and having performed the scoping parametric analyses from neutronics and thermal-hydraulic perspectives, it was necessary to focus on a particular application that would (1) demonstrate the viability of the overall concept and (2) require a reasonably structured design analysis process that would synthesize those important parameters that influence the concept the most as part of a feasible, working reactor system. Thus, the application targeted for this concept was supplying power for remote/harsh environments and a design that was easily deployable, simplistic from an operational standpoint, and utilized the new graphite foam. Specifically, a 500-kW(t) reactor concept was pursued that is naturally load following, inherently safe, optimized via neutronic studies to achieve near-zero reactivity change with burnup, and proliferation resistant. These four major areas

  16. Super critical water reactors

    International Nuclear Information System (INIS)

    Dumaz, P.; Antoni, O; Arnoux, P.; Bergeron, A; Renault, C.; Rimpault, G.

    2005-01-01

    Water is used as a calori-porter and moderator in the most major nuclear centers which are actually in function. In the pressurized water reactor (PWR) and boiling water reactor (BWR), water is maintained under critical point of water (21 bar, 374 Centigrade) which limits the efficiency of thermodynamic cycle of energy conversion (yield gain of about 33%) Crossing the critical point, one can then use s upercritical water , the obtained pressure and temperature allow a significant yield gains. In addition, the supercritical water offers important properties. Particularly there is no more possible coexistence between vapor and liquid. Therefore, we don't have more boiling problem, one of the phenomena which limits the specific power of PWR and BWR. Since 1950s, the reactor of supercritical water was the subject of studies more or less detailed but neglected. From the early 1990s, this type of conception benefits of some additional interests. Therefore, in the international term G eneration IV , the supercritical water reactors had been considered as one of the big options for study as Generation IV reactors. In the CEA, an active city has engaged from 1930 with the participation to a European program: The HPWR (High Performance Light Water Reactor). In this contest, the R and D studies are focused on the fields of neutrons, thermodynamic and materials. The CEA intends to pursue a limited effort of R and D in this field, in the framework of international cooperation, preferring the study of versions of rapid spectrum. (author)

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

    International Nuclear Information System (INIS)

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

    2014-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2014-07-01

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

  19. Plant maintenance and advanced reactors, 2006

    Energy Technology Data Exchange (ETDEWEB)

    Agnihotri, Newal (ed.)

    2006-09-15

    The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: Advanced plants to meet rising expectations, by John Cleveland, International Atomic Energy Agency, Vienna; A flexible and economic small reactor, by Mario D. Carelli and Bojan Petrovic, Westinghouse Electric Company; A simple and passively safe reactor, by Yury N. Kuznetsov, Research and Development Institute of Power Engineering (NIKIET), Russia; Gas-cooled reactors, by Jeffrey S. Merrifield, U.S. Nuclear Regulatory Commission; ISI project managment in the PRC, by Chen Chanbing, RINPO, China; and, Fort Calhoun refurbishment, by Sudesh Cambhir, Omaha Public Power District.

  20. U.S. activities related to fast reactors and ADS

    International Nuclear Information System (INIS)

    Finck, Phillip J.

    2001-01-01

    The U.S. nuclear power industry achieved its second straight year of record power generation levels during 2000. Total power generated was 753.9 billion kWh, 3.5 percent above the previous record of 728.1 billion kWh set in 1999. Recent years of reliable service and declining production costs have led to increased industry interest in nuclear power plant license renewal. The Nuclear Regulatory Commission approved the license renewal applications for five U.S. nuclear power plants in 2000. Five additional applications were received and 28 more are planned to be submitted by 2004. Concerns over energy resource availability, climate change, air quality, and energy security suggest an important role for nuclear power in future energy supplies. While the current Generation II and III nuclear power plant designs provide an economically, technically, and publicly acceptable electricity supply in many markets, further advances in nuclear energy system design can broaden the opportunities for the use of nuclear energy. To explore these opportunities, the U. S. Department of Energy's Office of Nuclear Energy, Science and Technology has engaged governments, industry, and the research community worldwide in a wide-ranging discussion on the development of next-generation nuclear energy systems known as 'Generation IV'. The I-NERI program has the following objectives: Develop advanced concepts and scientific breakthroughs in nuclear fission and reactor technology to address and overcome the principal technical and scientific obstacles to the expanded use of nuclear energy worldwide; Promote bilateral and multilateral collaboration with international agencies and research organizations to improve development of nuclear energy; and Promote and maintain nuclear science and engineering infrastructure to meet future technical challenges. I-NERI will sponsor innovative research and development in the following areas: Next-generation nuclear energy plant designs with higher efficiency

  1. Reactor power control device

    International Nuclear Information System (INIS)

    Ishii, Yoshihiko; Arita, Setsuo; Miyamoto, Yoshiyuki; Fukazawa, Yukihisa; Ishii, Kazuhiko

    1998-01-01

    The present invention provides a reactor power control device capable of enhancing an operation efficiency while keeping high reliability and safety in a BWR type nuclear power plant. Namely, the device of the present invention comprises (1) a means for inputting a set value of a generator power and a set value of a reactor power, (2) a means for controlling the reactor power to either smaller one of the reactor power corresponding to the set value of the generator power and the set value of the reactor power. With such procedures, even if the nuclear power plant is set so as to operate it to make the reactor power 100%, when the generator power reaches the upper limit, the reactor power is controlled with a preference given to the upper limit value of the generator power. Accordingly, safety and reliability are not deteriorated. The operation efficiency of the plant can be improved. (I.S.)

  2. The Simulator Development for RDE Reactor

    Science.gov (United States)

    Subekti, Muhammad; Bakhri, Syaiful; Sunaryo, Geni Rina

    2018-02-01

    BATAN is proposing the construction of experimental power reactor (RDE reactor) for increasing the public acceptance on NPP development plan, proofing the safety level of the most advanced reactor by performing safety demonstration on the accidents such as Chernobyl and Fukushima, and owning the generation fourth (G4) reactor technology. For owning the reactor technology, the one of research activities is RDE’s simulator development that employing standard equation. The development utilizes standard point kinetic and thermal equation. The examination of the simulator carried out comparison in which the simulation’s calculation result has good agreement with assumed parameters and ChemCAD calculation results. The transient simulation describes the characteristic of the simulator to respond the variation of power increase of 1.5%/min, 2.5%/min, and 3.5%/min.

  3. Research reactor job analysis - A project description

    International Nuclear Information System (INIS)

    Yoder, John; Bessler, Nancy J.

    1988-01-01

    Addressing the need of the improved training in nuclear industry, nuclear utilities established training program guidelines based on Performance-Based Training (PBT) concepts. The comparison of commercial nuclear power facilities with research and test reactors owned by the U.S. Department of Energy (DOE), made in an independent review of personnel selection, training, and qualification requirements for DOE-owned reactors pointed out that the complexity of the most critical tasks in research reactors is less than that in power reactors. The U.S. Department of Energy (DOE) started a project by commissioning Oak Ridge Associated Universities (ORAU) to conduct a job analysis survey of representative research reactor facilities. The output of the project consists of two publications: Volume 1 - Research Reactor Job Analysis: Overview, which contains an Introduction, Project Description, Project Methodology,, and. An Overview of Performance-Based Training (PBT); and Volume 2 - Research Reactor Job Analysis: Implementation, which contains Guidelines for Application of Preliminary Task Lists and Preliminary Task Lists for Reactor Operators and Supervisory Reactor Operators

  4. IAEA Laboratory activities. The IAEA Laboratories at Vienna and Seibersdorf, the International Laboratory of Marine Radioactivity at Monaco, the International Centre for Theoretical Physics at Trieste, the Middle Eastern Regional Radioisotope Centre for the Arab Countries, Cairo. Sixth report

    International Nuclear Information System (INIS)

    1969-01-01

    This sixth 'IAEA Laboratory Activities' report describes development and work during the year 1968. It includes activities of the IAEA Laboratories at Vienna and Seibersdorf, the International Laboratory of Marine Radioactivity at Monaco, the International Centre for Theoretical Physics at Trieste, and the Middle Eastern Regional Radioisotope Centre for the Arab Countries at Cairo. (author)

  5. IAEA Laboratory activities. The IAEA Laboratories at Vienna and Seibersdorf, the International Laboratory of Marine Radioactivity at Monaco, the International Centre for Theoretical Physics at Trieste, the Middle Eastern Regional Radioisotope Centre for the Arab Countries, Cairo. Fourth report

    International Nuclear Information System (INIS)

    1967-01-01

    This fourth 'IAEA Laboratory Activities' report describes development and work during the year 1966. It includes activities of the IAEA Laboratories at Vienna and Seibersdorf, the International Laboratory of Marine Radioactivity at Monaco, the International Centre for Theoretical Physics at Trieste, and the Middle Eastern Regional Radioisotope Centre for the Arab Countries at Cairo. (author)

  6. Reactor protection systems for the Replacement Research Reactor, ANSTO

    International Nuclear Information System (INIS)

    Morris, C.R.

    2003-01-01

    The 20-MW Replacement Research Reactor Project which is currently under construction at ANSTO will have a combination of a state of the art triplicated computer based reactor protection system, and a fully independent, and diverse, triplicated analogue reactor protection system, that has been in use in the nuclear industry, for many decades. The First Reactor Protection System (FRPS) consists of a Triconex triplicated modular redundant system that has recently been approved by the USNRC for use in the USA?s power reactor program. The Second Reactor Protection System is a hardwired analogue system supplied by Foxboro, the Spec 200 system, which is also Class1E qualified. The FRPS is used to drop the control rods when its safety parameter setpoints have been reached. The SRPS is used to drain the reflector tank and since this operation would result in a reactor poison out due to the time it would take to refill the tank the FRPS trip setpoints are more limiting. The FRPS and SRPS have limited hardwired indications on the control panels in the main control room (MCR) and emergency control centre (ECC), however all FRPS and SRPS parameters are capable of being displayed on the reactor control and monitoring system (RCMS) video display units. The RCMS is a Foxboro Series I/A control system which is used for plant control and monitoring and as a protection system for the cold neutron source. This paper will provide technical information on both systems, their trip logics, their interconnections with each other, and their integration into the reactor control and monitoring system and control panels. (author)

  7. GROUND PENETRATING RADAR INVESTIGATIONS FOR ARCHITECTURAL HERITAGE PRESERVATION OF THE HABIB SAKAKINI PALACE, CAIRO, EGYPT

    Directory of Open Access Journals (Sweden)

    Sayed HEMEDA

    2012-09-01

    Full Text Available The modern architectural heritage of Egypt is both varied and vast. It covers all nonecclesiastical buildings, important monumental structures (mansions, municipal buildings in the history of architecture, as well as more common buildings. They include houses (from mansions to simple dwellings, public buildings (schools, administrative buildings, hospitals, industrial buildings (factories, warehouses, mills, bridges, monastic dependencies (drinking foundations, gardens and any other modern structures that fall within the category of monuments and comprise the Egyptian cultural heritage. We present herein a comprehensive Ground Penetration Radar (GPR investigation and hazard assessment for the rehabilitation and strengthening of Habib Sakakini’s Palace, in Cairo, considered one of the most significant architectural heritage sites in Egypt. The palace is located on an ancient water pond at the eastern side of the Egyptian gulf, beside the Sultan Bebris Al-Bondoqdary mosque, a place also called “Prince Qraja al-Turkumany pond”. That pond was drained by Habib Sakakini in 1892, to construct his famous palace in 1897. Eight hundred meters of Ground Penetration Radar (GPR profiling were conducted, to monitor the subsurface conditions. 600 meters were made in the surrounding area of the Palace and 200 m at the basement. The aim was to monitor the soil conditions beneath and around the Palace and to identify potential geological discontinuities, or the presence of faults and cavities. A suitable single and dual antenna were used (500-100 MHZ to penetrate to the desired depth of 7 meters (ASTM D6432. The GPR was also used to detect the underground water. At the building basement the GPR was used to identify the foundation thickness and the soil - basement interface, as well as for the inspection of cracks in some supporting columns, piers and masonry walls. All the results, together with the seismic hazard analysis, will be used for a complete

  8. Plutonium-burn high temperature gas-cooled reactor for 3E+3S

    International Nuclear Information System (INIS)

    Okamoto, Koji

    2015-01-01

    The Nuclear Energy Development in Japan is facing a very difficult conditions after Fukushima-Daiichi NPP Accident. Nuclear Energy has strong advantages on 3E, i.e., Energy security, Economical efficiency and Environment. However, people does not believe the Safety 'S' of Nuclear Energy, now. The disadvantage of 'S' overrides the advantages of '3E'. In Nuclear Energy, 'S' is expanded into 3S, i.e., Safety, Security and Safeguards. Especially, the management of Plutonium inventory in Spent Fuel generated by the NPP operation is very important in the viewpoints of non-proliferation. The high-temperature gas cooled reactor (HTGR) is the solution of these disadvantages of '3S' in Nuclear Energy. The fuel of HTGR is composed by 1 mm spherical fuel particle, i.e., TRISO made by fuel, graphite and silicon-carbide. The silicon-carbide can confine the fission products in any conditions of fuel life cycle, i.e., during operation, accidents and disposal for 1 million years. The confinement of the radioactive materials can be confirmed by the TRISO. The HTGR core has strong negative feedback for temperature. So, the fission automatically stopped at the accidental conditions, such as loss of flow and LOCA. Also, the residual heat can be cooled by the radiation heat transfer to reactor vessel wall. The HTGR system usually has passive vessel wall cooling system. When the passive cooling system had been failed, the heat can be transferred to the land by heat conductions, and fuel does not reach the SiC broken temperature. The fission chain reaction has been stopped automatically by negative feedback, i.e., physics. The residual heat had been cooled automatically by radiation. The radioactive materials had been confined automatically by silicon-carbide. The HTGR is superior for 'S' safety. Plutonium can be burned by the HTGR. In the viewpoints of non-proliferation, the fuel should be made by YSZ-PuO 2 , stabilized buffer

  9. Nuclear reactors built, being built, or planned 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-08-01

    This publication contains unclassified information about facilities, built, being built, or planned in the United States for domestic use or export as of December 31, 1996. The Office of Scientific and Technical Information, U.S. Department of Energy, gathers this information annually from Washington headquarters, and field offices of DOE; from the U.S. Nuclear Regulatory Commission (NRC); from the U. S. reactor manufacturers who are the principal nuclear contractors for foreign reactor locations; from U.S. and foreign embassies; and from foreign governmental nuclear departments. The book consists of three divisions, as follows: (1) a commercial reactor locator map and tables of the characteristic and statistical data that follow; a table of abbreviations; (2) tables of data for reactors operating, being built, or planned; and (3) tables of data for reactors that have been shut down permanently or dismantled.

  10. Nuclear reactors built, being built, or planned: 1996

    International Nuclear Information System (INIS)

    1997-08-01

    This publication contains unclassified information about facilities, built, being built, or planned in the United States for domestic use or export as of December 31, 1996. The Office of Scientific and Technical Information, U.S. Department of Energy, gathers this information annually from Washington headquarters, and field offices of DOE; from the U.S. Nuclear Regulatory Commission (NRC); from the U. S. reactor manufacturers who are the principal nuclear contractors for foreign reactor locations; from U.S. and foreign embassies; and from foreign governmental nuclear departments. The book consists of three divisions, as follows: (1) a commercial reactor locator map and tables of the characteristic and statistical data that follow; a table of abbreviations; (2) tables of data for reactors operating, being built, or planned; and (3) tables of data for reactors that have been shut down permanently or dismantled

  11. Challenges in licensing a sodium-cooled advanced recycling reactor

    International Nuclear Information System (INIS)

    Levin, Alan E.

    2008-01-01

    As part of the Global Nuclear Energy Partnership (GNEP), the U.S. Department of Energy (DOE) has focused on the use of sodium-cooled fast reactors (SFRs) for the destruction of minor actinides derived from used reactor fuel. This approach engenders an array of challenges with respect to the licensing of the reactor: the U.S. Nuclear Regulatory Commission (NRC) has never completed the review of an application for an operating license for a sodium-cooled reactor. Moreover, the current U.S. regulatory structure has been developed to deal almost exclusively with light-water reactor (LWR) designs. Consequently, the NRC must either (1) develop a new regulatory process for SFRs, or (2) reinterpret the existing regulations to apply them, as appropriate, to SFR designs. During the 1980s and 1990s, the NRC conducted preliminary safety assessments of the Sodium Advanced Fast Reactor (SAFR) and the Power Reactor Innovative Small Module (PRISM) designs, and in that context, began to consider how to apply LWR-based regulations to SFR designs. This paper builds on that work to consider the challenges, from the reactor designer's point of view, associated with licensing an SFR today, considering (1) the evolution of SFR designs, (2) the particular requirements of reactor designs to meet GNEP objectives, and (3) the evolution of NRC regulations since the conclusion of the SAFR and PRISM reviews. (author)

  12. Download this PDF file

    African Journals Online (AJOL)

    Professor of Genetics (Cytogenetics), Faculty of Medicine, Ain Shams University, Cairo, Egypt. Hosam A Abdel-Ghany. Consultant of Medical Human Genetics, Medical Genetic Center, Ain Shams University, Cairo, Egypt. Nermin S Elsayed. Consultant of Medical Human Genetics, Medical Genetics Center, Ain Shams ...

  13. Role of Leisure Time Physical Activity in Cancer Prevention: Awareness and Practice among Medical Students at Cairo University

    Science.gov (United States)

    Amin, Tarek Tawfik; Mohamed Abdelmoaty, Alshaimaa; Fouad Abd El Badei, Alaa; Obaid, Hamzah Ahmed; Mohamed, Esraa Mowafy; abosheab, Alaa; Abdulkarim, Ali; Abdelsadek, Omar

    2017-01-01

    Background: Physical inactivity is accountable for a sizable proportion of breast and colorectal cancers and other non-communicable diseases. The higher the individual’s awareness about the protective role of physical activity (PA) in reducing chronic disease, the greater the adoption of PA will be. Objectives: To determine the level of leisure-time physical activity (LTPA) and awareness towards the role of LTPA in cancer prevention among a sample of Medical students at Cairo University, Egypt. Subjects and Methods: A cross-sectional study, with multistage sampling (a total of 519 students from second to six year students) and a self administered questionnaire covering the study objectives. Results: A significant decrease in the actual?? level of LTPA was noted with students’ year of enrollment at the medical school. However, their knowledge about roles of PA in preventing coronary heart, elevated blood pressure, and elevated cholesterol exceeded 80%, with steady increase in relation to the year of enrolment from the second to 6th years. Their knowledge about PA preventive influence for cancer was low irrespective of the year enrolment (32.2% for prevention of colon and 16.2% for breast cancers). The main sources of knowledge about the role of PA in cancer prevention were the internet and media (77%). Conclusion: The students demonstrated a decline in their LTPA coupled with poor knowledge about the role of LTPA in cancer prevention. Revision of the current curricula should be considered with inclusion of more information on the role of LTPA in cancer prevention to facilitate better awareness of medical students and through them their future patients. Creative Commons Attribution License

  14. MLR reactor

    International Nuclear Information System (INIS)

    Ryazantsev, E.P.; Egorenkov, P.M.; Nasonov, V.A.; Smimov, A.M.; Taliev, A.V.; Gromov, B.F.; Kousin, V.V.; Lantsov, M.N.; Radchenko, V.P.; Sharapov, V.N.

    1998-01-01

    The Material Testing Loop Reactor (MLR) development was commenced in 1991 with the aim of updating and widening Russia's experimental base to validate the selected directions of further progress of the nuclear power industry in Russia and to enhance its reliability and safety. The MLR reactor is the pool-type one. As coolant it applies light water and as side reflector beryllium. The direction of water circulation in the core is upward. The core comprises 30 FA arranged as hexagonal lattice with the 90-95 mm pitch. The central materials channel and six loop channels are sited in the core. The reflector includes up to 11 loop channels. The reactor power is 100 MW. The average power density of the core is 0.4 MW/I (maximal value 1.0 MW/l). The maximum neutron flux density is 7.10 14 n/cm 2 s in the core (E>0.1 MeV), and 5.10 14 n/cm 2 s in the reflector (E<0.625 eV). In 1995 due to the lack of funding the MLR designing was suspended. (author)

  15. On the yield of cold and ultracold neutrons for liquid hydrogen at low temperatures near the melting point

    CERN Document Server

    Morishima, N

    1999-01-01

    The neutron scattering cross sections for liquid hydrogen in the temperature range from the melting point to the boiling point are calculated. It is shown that lowering the temperature results in a significant increase in the yield of cold neutrons: for instance, a 44% increase for an incident neutron energy of 19.4 meV. The major cause of this increment is the para-to-ortho transition of a hydrogen molecule though accompanied by an appreciable increase in the density. The results of the cold- and ultracold-neutron yields are discussed in connection with the experimental results of Altarev et al. at the WWR-M reactor.

  16. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    A nuclear reactor containment vessel faced internally with a metal liner is provided with thermal insulation for the liner, comprising one or more layers of compressible material such as ceramic fiber, such as would be conventional in an advanced gas-cooled reactor and also a superposed layer of ceramic bricks or tiles in combination with retention means therefor, the retention means (comprising studs projecting from the liner, and bolts or nuts in threaded engagement with the studs) being themselves insulated from the vessel interior so that the coolant temperatures achieved in a High-Temperature Reactor or a Fast Reactor can be tolerated with the vessel. The layer(s) of compressible material is held under a degree of compression either by the ceramic bricks or tiles themselves or by cover plates held on the studs, in which case the bricks or tiles are preferably bedded on a yielding layer (for example of carbon fibers) rather than directly on the cover plates

  17. Nuclear Power: Outlook for New U.S. Reactors

    National Research Council Canada - National Science Library

    Parker, Larry; Holt, Mark

    2007-01-01

    Nearly three decades after the most recent order was placed for a new nuclear power plant in the United States, several utilities are now expressing interest in building a total of up to 30 new reactors...

  18. ''Sleeping reactor'' irradiations: Shutdown reactor determination of short-lived activation products

    International Nuclear Information System (INIS)

    Jerde, E.A.; Glasgow, D.C.

    1998-01-01

    At the High-Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory, the principal irradiation system has a thermal neutron flux (φ) of ∼ 4 x 10 14 n/cm 2 · s, permitting the detection of elements via irradiation of 60 s or less. Irradiations of 6 or 7 s are acceptable for detection of elements with half-lives of as little as 30 min. However, important elements such as Al, Mg, Ti, and V have half-lives of only a few minutes. At HFIR, these can be determined with irradiation times of ∼ 6 s, but the requirement of immediate counting leads to increased exposure to the high activity produced by irradiation in the high flux. In addition, pneumatic system timing uncertainties (about ± 0.5 s) make irradiations of 9 Be(γ,n) 8 Be, the gamma rays principally originating in the spent fuel. Upon reactor SCRAM, the flux drops to ∼ 1 x 10 10 n/cm 2 · s within 1 h. By the time the fuel elements are removed, the flux has dropped to ∼ 6 x 10 8 . Such fluxes are ideal for the determination of short-lived elements such as Al, Ti, Mg, and V. An important feature of the sleeping reactor is a flux that is not constant

  19. U.S. fast reactor materials and structures program

    International Nuclear Information System (INIS)

    Harms, W.O.; Purdy, C.M.

    1984-01-01

    The U.S. DOE has sponsored a vigorous breeder reactor materials and structures program for 15 years. Important contributions have resulted from this effort in the areas of design (inelastic rules, verified methods, seismic criteria, mechanical properties data); resolution of licensing issues (technical witnessing, confirmatory testing); construction (fabrication/welding procedures, nondestructive testing techniques); and operation (sodium purification, instrumentation and chemical analysis, radioactivity control, and in-service inspection. The national LMFBR program currently is being restructured. The Materials and Structures Program will focus its efforts in the following areas: (1) removal of anticipated licensing impediments through confirmation of the adequacy of structural design methods and criteria for components containing welds and geometric discontinuities, the generation of mechanical properties for stainless steel castings and weldments, and the evaluation of irradiation effects; (2) qualification of modified 9 Cr-1 Mo steel and tribological coatings for design flexibility; (3) development of improved inelastic design guidelines and procedures; (4) reform of design codes and standards and engineering practices, leading to simpler, less conservative rules and to simplified design analysis methods; and (5) incorporation of information from foreign program

  20. Preliminary results of robotic colorectal surgery at the National Cancer Institute, Cairo University

    International Nuclear Information System (INIS)

    Zaghloul, A.S.; Mahmoud, A.M.

    2016-01-01

    Background: The available literature on minimally invasive colorectal cancer demonstrates that laparoscopic approach is feasible and associated with better short term outcomes than open surgery while maintaining equivalent oncologic safety. Reports have shown that robotic surgery may overcome some of the pitfalls of laparoscopic intervention. Objective of the work: To evaluate early results of robotic colorectal surgery, in a cohort of Egyptian patients, regarding operative time, operative and early post-operative complications, hospital stay and pathological results. Patients and methods: A case series study which was carried out in surgical department at National Cancer Institute, Cairo University. Ten Egyptian cases of colorectal cancer (age ranged from 30 to 67, 5 males and 5 females) were recruited from the period of April 2013 to April 2014. Robotic surgery was performed to all cases. Results: Three patients had low anterior resection, three anterior resection, one total proctectomy, one abdominoperineal resection, one left hemicolectomy and one colostomy. The study reported no mortalities and two morbidities. The mean operative time was 333 min. The conversion to open was done in only one patient. A total mesorectal excision with negative circumferential margin was accomplished in all patients, distal margin was positive in one patient. Mean lymph nodes removed was 10.7. Mean hospital stay was 7.4 days. Conclusion: To the best of our knowledge, this is the first study reporting the outcomes of robotic colorectal cancer intervention in Egyptian patients. Our preliminary results suggest that robotic- assisted surgery for colorectal cancer can be carried out safely and according to oncological principles

  1. Participation in the U.S. Department of Energy Reactor Sharing Program. Progress report

    International Nuclear Information System (INIS)

    Mulder, R.U.; Benneche, P.E.; Hosticka, B.

    1997-03-01

    The objective of the DOE supported Reactor Sharing Program is to increase the availability of university nuclear reactor facilities to non-reactor-owning educational institutions. The educational and research programs of these user institutions is enhanced by the use of the nuclear facilities. Several methods have been used by the UVA Reactor Facility to achieve this objective. First, many college and secondary school groups toured the Reactor Facility and viewed the UVAR reactor and associated experimental facilities. Second, advanced undergraduate and graduate classes from area colleges and universities visited the facility to perform experiments in nuclear engineering and physics which would not be possible at the user institution. Third, irradiation and analysis services at the Facility have been made available for research by faculty and students from user institutions. Fourth, some institutions have received activated material from UVA for use at their institutions. These areas are discussed here

  2. Significance assessment of small-medium sized reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kanno, Minoru [Japan Atomic Power Co., Research and Development Dept., Tokyo (Japan)

    2002-12-01

    Preliminary assessment for deployment of small-medium sized reactor (S and M reactor) as a future option has been conducted at the JAPCO (Japan Atomic Power Company) under the cooperation with the CRIERI (Central Research Institute of Electric Power Industry). Significance of the S and M reactor introduction is listed as follows; lower investment cost, possible siting near demand side, enlarged freedom of siting, shorter transmission line, good compatibility with slow increase of demand and plain explanation of safety using simpler system such as integral type vessel without piping, natural convection core cooling and passive safety system. The deployment of simpler plant system, modular shop fabrication, ship-shell structured building and longer operation period can assure economics comparable with that of a large sized reactor, coping with scale-demerit. Also the S and M reactor is preferable in size for the nuclear heat utilization such as hydrogen production. (T. Tanaka)

  3. Lessons learned from 50 years period the storage of the spent fuel from nuclear research reactor VVR-S

    International Nuclear Information System (INIS)

    Dragusin, M.

    2010-01-01

    The nuclear research reactor VVR-S was commissioned in July 1957. This reactor is in permanent shutdown since December 1997 and will be decommissioned. The duration of the decommissioning project is 11 years. The first year of decommissioning project is 2010. The spent nuclear fuels resulting from the 40 years of operating the nuclear research reactor are stored under wet conditions. The chemical and physical water parameters monitored are: transparency, conductibility, pH, chloride content, oxygen content, temperature, dry residual content, Al, Mn, Mg, Fe, Vn, Cr. Residual dry content must be maintained in requested range in order to prevent degradation and corrosion both of the clads, assemblies and linen material of the ponds. Two types of the nuclear fuel assemblies were used: LEU type -EK-10 and HEU type S-36 Russian origin. All spent nuclear fuel assemblies HEU-S-36 type were repatriated in Russian Federation in June 2009 in safety and security conditions without any problems due of the wet storage, after 25 years storage in wet conditions. The spent nuclear fuel assemblies types LEU EK-10 were stored in wet conditions more than 50 years. This paper describes the lessons learned during the 50 years management of the spent nuclear fuel resulted from the operation the research reactor VVR-S. The management was based on the maintenance of water parameters by water filtration, using at all times air HEPA filter incorporated in technological ventilation system and by monitoring the level, temperature, physical and chemical parameters of the water storage from ponds and by controlling ponds linen physical integrity. Also we have used the discs having the same compositions with materials from assemblies stored in the same ponds, in order to verify degradation and corrosion phenomena induced due to the quality of storage water. The paper will described these results obtained by metallographic, visual, XRF analysis onto discs and dry residual samples from storage

  4. Strategy to support HTGR fuel for the 10 MW Indonesia’s experimental power reactor (RDE)

    International Nuclear Information System (INIS)

    Taswanda Taryo; Geni Rina Sunaryo; Ridwan; Meniek Rachmawati

    2018-01-01

    The Indonesia’s 10 MW experimental power reactor (RDE) is developed based on high temperature gas-cooled reactor (HTGR) and the program of the RDE was firstly introduced to the Agency for National Development Planning (BAPPENAS) at the beginning of 2014. The RDE program is expected to have positive impacts on community prosperity, self-reliance and sovereignty of Indonesia. The availability of RDE will be able to accelerate advanced nuclear power technology development and hence elevate Indonesia to be the nuclear champion in the ASEAN region. The RDE is expected to be operable in 2022/2023. In terms of fuel supply for the reactor, the first batch of RDE fuel will be inclusive in the RDE engineering, procurement and construction (RDE-EPC) contract for the assurance of the RDE reactor operation from 2023 to 2027. Consideration of RDE fuel plant construction is important as RDE can be the basis for the development of reactors of similar type with small-medium power(25 MWe–200/300 MWe), which are preferable for eastern part of Indonesia. To study the feasibility of the construction of RDE fuel plant, current state of the art of the R&D on HTGR fuel in some advanced countries such as European countries, the United States, South Africa and Japan will be discussed and overviewed to draw a conclusion about the prospective countries for supporting the fuel for long-term RDE operation. The strategy and road map for the preparation of the RDE fuel plant construction with the involvement of national stake holders have been developed. The best possible vendor country to support HTGR fuel for long-term operation is finally accomplished. In the end, this paper can be assigned as a reference for the planning and construction of HTGR RDE fuel fabrication plant in Indonesia. (author)

  5. IAEA laboratory activities. The IAEA laboratories at Vienna and Seibersdorf, the International Laboratory of Marine Radioactivity at Monaco, the International Centre for Theoretical Physics at Trieste, the Middle Eastern Regional Radioisotope Centre for the Arab Countries, Cairo. 3rd report

    International Nuclear Information System (INIS)

    1966-01-01

    This third 'IAEA Laboratory Activities' report describes development and work during the year 1965. It includes activities of the IAEA Laboratories at Vienna and Seibersdorf, the International Laboratory of Marine Radioactivity at Monaco, the International Centre for Theoretical Physics at Trieste, and the Middle Eastern Regional Radioisotope Centre for the Arab Countries at Cairo

  6. Status of the advanced boiling water reactor and simplified boiling water reactor

    International Nuclear Information System (INIS)

    Smith, P.F.

    1992-01-01

    This paper reports that the excess of U.S. electrical generating capacity which has existed for the past 15 years is coming to an end as we enter the 1990s. Environmental and energy security issues associated with fossil fuels are kindling renewed interest in the nuclear option. The importance of these issues are underscored by the National Energy Strategy (NES) which calls for actions which are designed to ensure that the nuclear power option is available to utilities. Utilities, utility associations, and nuclear suppliers, under the leadership of the Nuclear Power Oversight Committee (NPOC), have jointly developed a 14 point strategic plan aimed at establishing a predictable regulatory environment, standardized and pre-licensed Advanced Light Water Reactor (ALWR) nuclear plants, resolving the long-term waste management issue, and other enabling conditions. GE is participating in this national effort and GE's family of advanced nuclear power plants feature two new reactor designs, developed on a common technology base, aimed at providing a new generation of nuclear plants to provide safe, clean, economical electricity to the world's utilities in the 1990s and beyond. Together, the large-size (1300 MWe) Advanced Boiling Water Reactor (ABWR) and the small-size (600 MWe) Simplified Boiling Water Reactor (SBWR) are innovative, near-term candidates for expanding electrical generating capacity in the U.S. and worldwide. Both possess the features necessary to do so safely, reliably, and economically

  7. Research reactors: a tool for science and medicine; Reactores de investigacion: herramientas para la ciencia y la medicina

    Energy Technology Data Exchange (ETDEWEB)

    Ordonez, Juan [Investigacion Aplicada SE (INVAP), San Carlos de Bariloche (Argentina)

    2001-07-01

    The types and uses of research reactors are reviewed. After an analysis of the world situation, the demand of new research reactors of about 20 MW is foreseen. The experience and competitiveness of INVAP S.E. as designer and constructor of research reactors is outlined and the general specifications of the reactors designed by INVAP for Egypt and Australia are given.

  8. Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems

    Energy Technology Data Exchange (ETDEWEB)

    D. E. Shropshire

    2009-01-01

    The Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems, prepared to support the U.S. Advanced Fuel Cycle Initiative (AFCI) systems analysis, provides a technology-oriented baseline system cost comparison between the open fuel cycle and closed fuel cycle systems. The intent is to understand their overall cost trends, cost sensitivities, and trade-offs. This analysis also improves the AFCI Program’s understanding of the cost drivers that will determine nuclear power’s cost competitiveness vis-a-vis other baseload generation systems. The common reactor-related costs consist of capital, operating, and decontamination and decommissioning costs. Fuel cycle costs include front-end (pre-irradiation) and back-end (post-iradiation) costs, as well as costs specifically associated with fuel recycling. This analysis reveals that there are large cost uncertainties associated with all the fuel cycle strategies, and that overall systems (reactor plus fuel cycle) using a closed fuel cycle are about 10% more expensive in terms of electricity generation cost than open cycle systems. The study concludes that further U.S. and joint international-based design studies are needed to reduce the cost uncertainties with respect to fast reactor, fuel separation and fabrication, and waste disposition. The results of this work can help provide insight to the cost-related factors and conditions needed to keep nuclear energy (including closed fuel cycles) economically competitive in the U.S. and worldwide. These results may be updated over time based on new cost information, revised assumptions, and feedback received from additional reviews.

  9. Possibilities of TWR and long life reactor

    International Nuclear Information System (INIS)

    Sekimoto, Hiroshi; Shimazu, Yoichiro; Handa, Norihiko

    2010-01-01

    Bill Gates identified the need to switch to zero-emission energy and clarified investing in Terra Power developing the TWR (Traveling Wave Reactor) in February 2010. He also visited Toshiba developing small reactor 4S (Super Safe Small and Simple). In Japan design studies of the TWR have been conducted on the CANDLE reactor without refueling and the 4S long life reactor with maintenance free. In this feature article, the state of R and D on the TWR in Japan and IAEA's activities on small reactors without online refueling were reviewed in addition to articles on impacts of Bill Gates' investment in the TWR and state of the TWR development from an interview with John Gilleland of Terra Power. (T. Tanaka)

  10. LBB application in the US operating and advanced reactors

    Energy Technology Data Exchange (ETDEWEB)

    Wichman, K.; Tsao, J.; Mayfield, M.

    1997-04-01

    The regulatory application of leak before break (LBB) for operating and advanced reactors in the U.S. is described. The U.S. Nuclear Regulatory Commission (NRC) has approved the application of LBB for six piping systems in operating reactors: reactor coolant system primary loop piping, pressurizer surge, safety injection accumulator, residual heat removal, safety injection, and reactor coolant loop bypass. The LBB concept has also been applied in the design of advanced light water reactors. LBB applications, and regulatory considerations, for pressurized water reactors and advanced light water reactors are summarized in this paper. Technology development for LBB performed by the NRC and the International Piping Integrity Research Group is also briefly summarized.

  11. U.S. Department of Energy University Reactor Sharing Program at the University of Florida. Final report for period August 15, 2000 - May 31, 2001

    Energy Technology Data Exchange (ETDEWEB)

    Vernetson, William G.

    2002-01-01

    Department of Energy Grant Number DE-FG02-96NE38152 was supplied to the University of Florida Training Reactor (UFTR) facility through the U.S. Department of Energy's University Reactor Sharing Program. The renewal proposal submitted in January 2000 originally requested over $73,000 to support various external educational institutions using the UFTR facilities in academic year 2000-01. The actual Reactor Sharing Grant was only in the amount of $40,000, all of which has been well used by the University of Florida as host institution to support various educational institutions in the use of our reactor and associated facilities as indicated in the proposal. These various educational institutions are located primarily within the State of Florida. However, when the 600-mile distance from Pensacola to Miami is considered, it is obvious that this Grant provides access to reactor utilization for a broad geographical region and a diverse set of user institutions serving over fourteen million inhabitants throughout the State of Florida and still others throughout the Southeast.

  12. Advanced Demonstration and Test Reactor Options Study

    Energy Technology Data Exchange (ETDEWEB)

    Petti, David Andrew [Idaho National Lab. (INL), Idaho Falls, ID (United States); Hill, R. [Argonne National Lab. (ANL), Argonne, IL (United States); Gehin, J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gougar, Hans David [Idaho National Lab. (INL), Idaho Falls, ID (United States); Strydom, Gerhard [Idaho National Lab. (INL), Idaho Falls, ID (United States); Heidet, F. [Argonne National Lab. (ANL), Argonne, IL (United States); Kinsey, J. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Grandy, Christopher [Argonne National Lab. (ANL), Argonne, IL (United States); Qualls, A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Powers, J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Hoffman, E. [Argonne National Lab. (ANL), Argonne, IL (United States); Croson, D. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2017-01-01

    Global efforts to address climate change will require large-scale decarbonization of energy production in the United States and elsewhere. Nuclear power already provides 20% of electricity production in the United States (U.S.) and is increasing in countries undergoing rapid growth around the world. Because reliable, grid-stabilizing, low emission electricity generation, energy security, and energy resource diversity will be increasingly valued, nuclear power’s share of electricity production has a potential to grow. In addition, there are non electricity applications (e.g., process heat, desalination, hydrogen production) that could be better served by advanced nuclear systems. Thus, the timely development, demonstration, and commercialization of advanced nuclear reactors could diversify the nuclear technologies available and offer attractive technology options to expand the impact of nuclear energy for electricity generation and non-electricity missions. The purpose of this planning study is to provide transparent and defensible technology options for a test and/or demonstration reactor(s) to be built to support public policy, innovation and long term commercialization within the context of the Department of Energy’s (DOE’s) broader commitment to pursuing an “all of the above” clean energy strategy and associated time lines. This planning study includes identification of the key features and timing needed for advanced test or demonstration reactors to support research, development, and technology demonstration leading to the commercialization of power plants built upon these advanced reactor platforms. This planning study is consistent with the Congressional language contained within the fiscal year 2015 appropriation that directed the DOE to conduct a planning study to evaluate “advanced reactor technology options, capabilities, and requirements within the context of national needs and public policy to support innovation in nuclear energy

  13. The status of the PIK reactor

    Energy Technology Data Exchange (ETDEWEB)

    Petrov, Yu V [Academy of Sciences of Russia, Petersburg Nuclear Physics Institute, Gatchina, St. Petersburg (Russian Federation)

    1992-07-01

    This report describes the 100 MW research reactor PIK which is now under construction. The thermal neutron flux in the heavy water reflector exceeds 10{sup 15} cm{sup -2}s{sup -1}; in the light water trap, it is about 4{center_dot}10{sup 15} cm{sup -2}s{sup -1}. The replaceable core vessel allows to vary the parameters of the core over a wide range. The reactor provides sources of hot, cold and ultracold neutrons for 10 horizontal, 6 inclined neutron beams, and 8 neutron guides. At the ends of the beam tubes, the neutron flux is 10{sup 10} - 10{sup 11} cm{sup -2}s{sup -1}. The flux of the long wave neutrons exceeds 10{sup 9} cm{sup -2}s{sup -1}. To ensure precise measurements, the experimental hall is protected against vibrations. The project meets all modern safety requirements. The calculated parameters of the reactor were verified using a full-scale mock-up. Seventy percent of the reactor construction and installation were completed in the beginning of 1992. (author)

  14. Commercial U.S. Vendors Focus on Reducing the Cost of Fast Reactors

    International Nuclear Information System (INIS)

    Fraser, Dan; Kouhestani, Amir; Parmentola, John; Prince, Robert; Reynolds, Roger

    2013-01-01

    A US commercial perspective: • Focus on economic benefits of fast reactors (Market Determined): • Compact design, high energy density (modularity); • High temperature output; • Improved energy conversion efficiency; • Process heat application market; • Inherent safety capabilities. • Focus on burn or “breed and burn”; • Helps avoid some non-proliferation challenges. • Focus on reactor alone, not on a re-processing plant; • Reactor is the first place for economic payback; • Happy to burn reprocessed fuel if available

  15. Structural and frequency dependencies of a.c. and dielectric ...

    Indian Academy of Sciences (India)

    Solid State Physics Department, Physics Division, National Research Center, Dokki, Giza 12311, Egypt; Electronics Department, Military Technical College, Cairo 11371, Egypt; Department of Engineering Applications of Laser (E.A.L), National Institute of Laser Enhanced Sciences (N.I.L.E.S), Cairo University, Giza 12613, ...

  16. The advanced MAPLE reactor concept

    International Nuclear Information System (INIS)

    Lidstone, R.F.; Lee, A.G.; Gillespie, G.E.; Smith, H.J.

    1989-01-01

    High-flux neutron sources are continuing to be of interest both in Canada and internationally to support materials testing for advanced power reactors, new developments in extracted-neutron-beam applications, and commercial production of selected radioisotopes. The advanced MAPLE reactor concept has been developed to meet these needs. The advanced MAPLE reactor is a new tank-type D 2 O reactor that uses rodded low-enrichment uranium fuel in a compact annular core to generate peak thermal-neutron fluxes of 1 x 10 19 n·s -1 in a central irradiation rig with a thermal power output of 50 MW. Capital and incremental development costs are minimized by using MAPLE reactor technology to the greatest extent practicable

  17. Reactor Dosimetry State of the Art 2008

    Science.gov (United States)

    Voorbraak, Wim; Debarberis, Luigi; D'Hondt, Pierre; Wagemans, Jan

    2009-08-01

    Oral session 1: Retrospective dosimetry. Retrospective dosimetry of VVER 440 reactor pressure vessel at the 3rd unit of Dukovany NPP / M. Marek ... [et al.]. Retrospective dosimetry study at the RPV of NPP Greifswald unit 1 / J. Konheiser ... [et al.]. Test of prototype detector for retrospective neutron dosimetry of reactor internals and vessel / K. Hayashi ... [et al.]. Neutron doses to the concrete vessel and tendons of a magnox reactor using retrospective dosimetry / D. A. Allen ... [et al.]. A retrospective dosimetry feasibility study for Atucha I / J. Wagemans ... [et al.]. Retrospective reactor dosimetry with zirconium alloy samples in a PWR / L. R. Greenwood and J. P. Foster -- Oral session 2: Experimental techniques. Characterizing the Time-dependent components of reactor n/y environments / P. J. Griffin, S. M. Luker and A. J. Suo-Anttila. Measurements of the recoil-ion response of silicon carbide detectors to fast neutrons / F. H. Ruddy, J. G. Seidel and F. Franceschini. Measurement of the neutron spectrum of the HB-4 cold source at the high flux isotope reactor at Oak Ridge National Laboratory / J. L. Robertson and E. B. Iverson. Feasibility of cavity ring-down laser spectroscopy for dose rate monitoring on nuclear reactor / H. Tomita ... [et al.]. Measuring transistor damage factors in a non-stable defect environment / D. B. King ... [et al.]. Neutron-detection based monitoring of void effects in boiling water reactors / J. Loberg ... [et al.] -- Poster session 1: Power reactor surveillance, retrospective dosimetry, benchmarks and inter-comparisons, adjustment methods, experimental techniques, transport calculations. Improved diagnostics for analysis of a reactor pulse radiation environment / S. M. Luker ... [et al.]. Simulation of the response of silicon carbide fast neutron detectors / F. Franceschini, F. H. Ruddy and B. Petrović. NSV A-3: a computer code for least-squares adjustment of neutron spectra and measured dosimeter responses / J. G

  18. Egypt: Background and U.S. Relations

    Science.gov (United States)

    2016-02-25

    exhortations to report critics of the government to the authorities; and censorship , prosecution, and attacks on journalists.” 19  Reporters Without...upon between the above-mentioned representatives.” See Agreement between the United States of America and Egypt, signed at Cairo, August 16, 1978

  19. Health physics aspects of advanced reactor licensing reviews

    International Nuclear Information System (INIS)

    Hinson, C.S.

    1995-01-01

    The last Construction Permit to be issued by the U.S. Nuclear Regulatory Commission (NRC) for a U.S. light water reactor (LWR) was granted in the late 1970s. In 1989 the NRC issued 10 CFR Part 52 which is intended to serve as a framework for the licensing of future reactor designs. The NRC is currently reviewing four different future on open-quotes next-generationclose quotes reactor designs. Two of these designs are classified as evolutionary designs (modified versions of current generation LWRs) and two are advanced designs (reactors incorporating simplified designs and passive means for accident mitigation). These open-quotes next-generationclose quotes reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four open-quotes next-generationclose quotes reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four open-quotes next-generationclose quotes reactor designs currently being reviewed by the NRC

  20. Reactor-specific spent fuel discharge projections, 1987-2020

    International Nuclear Information System (INIS)

    Walling, R.C.; Heeb, C.M.; Purcell, W.L.

    1988-03-01

    The creation of five reactor-specific spent fuel data bases that contain information on the projected amounts of spent fuel to be discharged from U.S. commercial nuclear reactors through the year 2020 is described. The data bases contain detailed spent fuel information from existing, planned, and projected pressurized water reactors (PWR) and boiling water eactors (BWR), and one existing high temperature gas reactor (HTGR). The projections are based on individual reactor information supplied by the U.S. reactor owners. The basic information is adjusted to conform to Energy Information Administration (EIA) forecasts for nuclear installed capacity, generation, and spent fuel discharged. The EIA cases considered are: No New Orders (assumes increasing burnup), No New Orders with No Increased Burnup, Upper Reference (assumes increasing burnup), Upper Reference with No Increased Burnup, and Lower Reference (assumes increasing burnup). Detailed, by-reactor tables are provided for annual discharged amounts of spent fuel, for storage requirements assuming maximum at-reactor storage, and for storage requirements assuming maximum at-reactor storage plus intra-utility transshipment of spent fuel. 8 refs., 8 figs., 10 tabs

  1. Reactor water level control device

    International Nuclear Information System (INIS)

    Utagawa, Kazuyuki.

    1993-01-01

    A device of the present invention can effectively control fluctuation of a reactor water level upon power change by reactor core flow rate control operation. That is, (1) a feedback control section calculates a feedwater flow rate control amount based on a deviation between a set value of a reactor water level and a reactor water level signal. (2) a feed forward control section forecasts steam flow rate change based on a reactor core flow rate signal or a signal determining the reactor core flow rate, to calculate a feedwater flow rate control amount which off sets the steam flow rate change. Then, the sum of the output signal from the process (1) and the output signal from the process (2) is determined as a final feedwater flow rate control signal. With such procedures, it is possible to forecast the steam flow rate change accompanying the reactor core flow rate control operation, thereby enabling to conduct preceding feedwater flow rate control operation which off sets the reactor water level fluctuation based on the steam flow rate change. Further, a reactor water level deviated from the forecast can be controlled by feedback control. Accordingly, reactor water level fluctuation upon power exchange due to the reactor core flow rate control operation can rapidly be suppressed. (I.S.)

  2. Reactor use in nuclear engineering programs

    International Nuclear Information System (INIS)

    Murray, R.L.

    1975-01-01

    Nuclear reactors for dual use in training and research were established at about 50 universities in the period since 1950, with assistance by the U. S. Atomic Energy Commission and the National Science Foundation. Most of the reactors are in active use for a variety of educational functions--laboratory teaching of undergraduates and graduate students, graduate research, orientation of visitors, and nuclear power plant reactor operator training, along with service to the technical community. As expected, the higher power reactors enjoy a larger average weekly use. Among special programs are reactor sharing and high-school teachers' workshops

  3. Risk Management for Sodium Fast Reactors.

    Energy Technology Data Exchange (ETDEWEB)

    Denman, Matthew R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Groth, Katrina [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Cardoni, Jeffrey N. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wheeler, Timothy A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-01-01

    Accident management is an important component to maintaining risk at acceptable levels for all complex systems, such as nuclear power plants. With the introduction of self - correcting, or inherently safe, reactor designs the focus has shifted from management by operators to allowing the syste m's design to manage the accident. While inherently and passively safe designs are laudable, extreme boundary conditions can interfere with the design attributes which facilitate inherent safety , thus resulting in unanticipated and undesirable end states. This report examines an inherently safe and small sodium fast reactor experiencing a beyond design basis seismic event with the intend of exploring two issues : (1) can human intervention either improve or worsen the potential end states and (2) can a Bayes ian Network be constructed to infer the state of the reactor to inform (1). ACKNOWLEDGEMENTS The author s would like to acknowledge the U.S. Department of E nergy's Office of Nuclear Energy for funding this research through Work Package SR - 14SN100303 under the Advanced Reactor Concepts program. The authors also acknowledge the PRA teams at A rgonne N ational L aborator y , O ak R idge N ational L aborator y , and I daho N ational L aborator y for their continue d contributions to the advanced reactor PRA mission area.

  4. Lessons from early experience in reactor development

    International Nuclear Information System (INIS)

    Allen, W.

    1976-09-01

    This paper deals with several issues in U.S. reactor development and demonstration experience. The focus is on the period between 1946 and 1963 during which the Atomic Energy Commission (AEC) guided early reactor research and development (R and D) and conducted the Power Reactor Demonstration Program

  5. Lessons learned from the shut down, planning, and the preparatory activities of decommissioning the research reactor VVR-S Magurele, Bucharest

    International Nuclear Information System (INIS)

    Dragusin, M.; Copaciu, V.

    2006-01-01

    The nuclear research reactor type VVR was shut down in December 1997 after forty years of operation. The main characteristics of this reactor are: Thermal power 2 MW, Thermal energy - 9.59 GWhd, Average flux of thermal neutrons-10 13 n/cm 2 .s, nine horizontal channels, sixteen vertical exposure channels, three biological channels, reactor type tank, water used as a moderator, coolant and reflector. The reactor was used in research and radioisotope production. The reactor has been permanently shut down since April 2002, when the decommissioning was officially announced. Discussions regarding funding mechanisms for the conservation phase, and decommissioning (planning, preparatory activities, spent nuclear fuel management), have taken place since five years ago when the final decision of permanent shut down was taken. Quality management includes procedures for recording and archiving the lessons learned. The planning of decommissioning started in 1990 when the reactor was still operational. After fifteen years the regulatory body has not yet approved the decommissioning plan for the reactor. In this paper the following aspects are discussed: decommissioning strategy from safe enclosure to immediate dismantling, specific features of the site (treatment of radioactive waste near reactor) and state of decommissioning, use of the lessons learned in the planning of decommissioning for the other two small nuclear facilities situated in the same area with VVR-reactor: Sub critical Assembly 'HELEN' and Zero Power Critical Reactor RP-0, AFR ponds for spent nuclear fuel, other radiological facilities for radioisotopes production facilities radiation processing and accelerators. Preparatory activities for decommissioning have included: elaboration of a plan (inter alia, justification of the selected strategy, management of the radioactive waste in accordance with the waste acceptance criteria), reactor storage in parallel with the removal of the equipment and materials used in

  6. Fuel assembly for FBR type reactor and reactor core thereof

    International Nuclear Information System (INIS)

    Kobayashi, Kaoru.

    1998-01-01

    The present invention provides a fuel assembly to be loaded to a reactor core of a large sized FBR type reactor, in which a coolant density coefficient can be reduced without causing power peaking in the peripheral region of neutron moderators loaded in the reactor core. Namely, the fuel assembly for the FBR type reactor comprises a plurality of fission product-loaded fuel rods and a plurality of fertile material-loaded fuel rods and one or more rods loading neutron moderators. In this case, the plurality of fertile material-loaded fuel rods are disposed to the peripheral region of the neutron moderator-loaded rods. The plurality of fission product-loaded fuel rods are disposed surrounding the peripheral region of the plurality of fertile material-loaded fuel rods. The neutron moderator comprises zirconium hydride, yttrium hydride and calcium hydride. The fission products are mixed oxide fuels. The fertile material comprises depleted uranium or natural uranium. (I.S.)

  7. Multi-purpose reactor

    International Nuclear Information System (INIS)

    1991-05-01

    The Multi-Purpose-Reactor (MPR), is a pool-type reactor with an open water surface and variable core arrangement. Its main feature is plant safety and reliability. Its power is 22MW t h, cooled by light water and moderated by beryllium. It has platetype fuel elements (MTR type, approx. 20%. enriched uranium) clad in aluminium. Its cobalt (Co 60 ) production capacity is 50000 Ci/yr, 200 Ci/gr. The distribution of the reactor core and associated control and safety systems is essentially based on the following design criteria: - upwards cooling flow, to waive the need for cooling flow inversion in case the reactor is cooled by natural convection if confronted with a loss of pumping power, and in order to establish a superior heat transfer potential (a higher coolant saturation temperature); - easy access to the reactor core from top of pool level with the reactor operating at full power, in order to facilitate actual implementation of experiments. Consequently, mechanisms associated to control and safety rods s,re located underneath the reactor tank; - free access of reactor personnel to top of pool level with the reactor operating at full power. This aids in the training of personnel and the actual carrying out of experiments, hence: - a vast water column was placed over the core to act as radiation shielding; - the core's external area is cooled by a downwards flow which leads to a decay tank beyond the pool (for N 16 to decay); - a small downwards flow was directed to stream downwards from above the reactor core in order to drag along any possibly active element; and - a stagnant hot layer system was placed at top of pool level so as to minimize the upwards coolant flow rising towards pool level

  8. Reactor container cooling device

    Energy Technology Data Exchange (ETDEWEB)

    Ando, Koji; Kinoshita, Shoichiro

    1995-11-10

    The device of the present invention efficiently lowers pressure and temperature in a reactor container upon occurrence of a severe accident in a BWR-type reactor and can cool the inside of the container for a long period of time. That is, (1) pipelines on the side of an exhaustion tower of a filter portion in a filter bent device of the reactor container are in communication with pipelines on the side of a steam inlet of a static container cooling device by way of horizontal pipelines, (2) a back flow check valve is disposed to horizontal pipelines, (3) a steam discharge valve for a pressure vessel is disposed closer to the reactor container than the joint portion between the pipelines on the side of the steam inlet and the horizontal pipelines. Upon occurrence of a severe accident, when the pressure vessel should be ruptured and steams containing aerosol in the reactor core should be filled in the reactor container, the inlet valve of the static container cooling device is closed. Steams are flown into the filter bent device of the reactor container, where the aerosols can be removed. (I.S.).

  9. The Jules Horowitz reactor project, a driver for revival of the research reactor community

    Energy Technology Data Exchange (ETDEWEB)

    Pere, P.; Cavailler, C.; Pascal, C. [AREVA TA, CEA Cadarache - Etablissement d' AREVA TA - Chantier RJH - MOE - BV2 - BP no. 9 - 13115 Saint Paul lez Durance (France); CS 50497 - 1100, rue JR Gauthier de la Lauziere, 13593 Aix en Provence cedex 3 (France)

    2010-07-01

    The first concrete of the nuclear island for the Jules Horowitz Reactor (JHR) was poured at the end of July 2009 and construction is ongoing. The JHR is the largest new platform for irradiation experiments supporting Generation II and III reactors, Generation IV technologies, and radioisotope production. This facility, composed of a unique grouping of workshops, hot cells and hot laboratories together with a first -rate MTR research reactor, will ensure that the process, from preparations for irradiation experiments through post-irradiation non-destructive examination, is completed expediently, efficiently and, of course, safely. In addition to the performance requirements to be met in terms of neutron fluxes on the samples (5x10{sup 14} n.cm{sup -2}/sec{sup -1} E> 1 MeV in core and 3,6x10{sup 14} n.cm{sup -2}/sec{sup -1} E<0.625 eV in the reflector) and the JHR's considerable irradiation capabilities (more than 20 experiments and one-tenth of irradiation area for simultaneous radioisotope production), the JHR is the first MTR to be built since the end of the 1960's, making this an especially challenging project. The presentation will provide an overview of the reactor, hot cells and laboratories and an outline of the key milestones in the project schedule, including initial criticality in early 2014 and radioisotope production in 2015. This will be followed by a description of the project organization set up by the CEA as owner and future operator and AREVA TA as prime contractor and supplier of critical systems, and a discussion of project challenges, especially those dealing with the following items: - accommodation of a broad experimental domain, - involvement by international partners making in-kind contributions to the project, - development of components critical to safety and performance, - the revival of engineering of research reactors and experimental devices involving France's historical players in the field of research reactors, and

  10. Toward a Mechanistic Source Term in Advanced Reactors: A Review of Past U.S. SFR Incidents, Experiments, and Analyses

    Energy Technology Data Exchange (ETDEWEB)

    Bucknor, Matthew; Brunett, Acacia J.; Grabaskas, David

    2016-04-17

    In 2015, as part of a Regulatory Technology Development Plan (RTDP) effort for sodium-cooled fast reactors (SFRs), Argonne National Laboratory investigated the current state of knowledge of source term development for a metal-fueled, pool-type SFR. This paper provides a summary of past domestic metal-fueled SFR incidents and experiments and highlights information relevant to source term estimations that were gathered as part of the RTDP effort. The incidents described in this paper include fuel pin failures at the Sodium Reactor Experiment (SRE) facility in July of 1959, the Fermi I meltdown that occurred in October of 1966, and the repeated melting of a fuel element within an experimental capsule at the Experimental Breeder Reactor II (EBR-II) from November 1967 to May 1968. The experiments described in this paper include the Run-Beyond-Cladding-Breach tests that were performed at EBR-II in 1985 and a series of severe transient overpower tests conducted at the Transient Reactor Test Facility (TREAT) in the mid-1980s.

  11. Radioactive waste management for reactors

    International Nuclear Information System (INIS)

    Rodger, W.A.

    1974-01-01

    Radioactive waste management practices at nuclear power plants are summarized. The types of waste produced and methods for treating various types of wastes are described. The waste management systems, including simplified flow diagrams, for typical boiling water reactors and pressurized water reactors are discussed. (U.S.)

  12. Nuclear Reactors and Technology; (USA)

    Energy Technology Data Exchange (ETDEWEB)

    Cason, D.L.; Hicks, S.C. (eds.)

    1991-01-01

    Nuclear Reactors and Technology (NRT) announces on a monthly basis the current worldwide information available from the open literature on nuclear reactors and technology, including all aspects of power reactors, components and accessories, fuel elements, control systems, and materials. This publication contains the abstracts of DOE reports, journal articles, conference papers, patents, theses, and monographs added to the Energy Science and Technology Database (EDB) during the past month. Also included are US information obtained through acquisition programs or interagency agreements and international information obtained through the International Energy Agency's Energy Technology Data Exchange or government-to-government agreements. The digests in NRT and other citations to information on nuclear reactors back to 1948 are available for online searching and retrieval on EDB and Nuclear Science Abstracts (NSA) database. Current information, added daily to EDB, is available to DOE and its contractors through the DOE integrated Technical Information System. Customized profiles can be developed to provide current information to meet each user's needs.

  13. Anaerobic treatment of winery wastewater in fixed bed reactors.

    Science.gov (United States)

    Ganesh, Rangaraj; Rajinikanth, Rajagopal; Thanikal, Joseph V; Ramanujam, Ramamoorty Alwar; Torrijos, Michel

    2010-06-01

    The treatment of winery wastewater in three upflow anaerobic fixed-bed reactors (S9, S30 and S40) with low density floating supports of varying size and specific surface area was investigated. A maximum OLR of 42 g/l day with 80 +/- 0.5% removal efficiency was attained in S9, which had supports with the highest specific surface area. It was found that the efficiency of the reactors increased with decrease in size and increase in specific surface area of the support media. Total biomass accumulation in the reactors was also found to vary as a function of specific surface area and size of the support medium. The Stover-Kincannon kinetic model predicted satisfactorily the performance of the reactors. The maximum removal rate constant (U(max)) was 161.3, 99.0 and 77.5 g/l day and the saturation value constant (K(B)) was 162.0, 99.5 and 78.0 g/l day for S9, S30 and S40, respectively. Due to their higher biomass retention potential, the supports used in this study offer great promise as media in anaerobic fixed bed reactors. Anaerobic fixed-bed reactors with these supports can be applied as high-rate systems for the treatment of large volumes of wastewaters typically containing readily biodegradable organics, such as the winery wastewater.

  14. Biodegradation of a commercial mixture of the herbicides atrazine and S-metolachlor in a multi-channel packed biofilm reactor.

    Science.gov (United States)

    Cabrera-Orozco, Alberto; Galíndez-Nájera, Silvia Patricia; Ruiz-Ordaz, Nora; Galíndez-Mayer, Juvencio; Martínez-Jerónimo, Fernando

    2017-11-01

    Atrazine and S-metolachlor are two of the most widely used herbicides for agricultural purposes; consequently, residues of both compounds and their metabolites had been detected in ground and superficial waters. Unlike atrazine, the complete degradation of metolachlor has not been achieved. Hence, the purpose of this research is to study the biodegradation of a commercial mixture of atrazine and S-metolachlor in a prototype of a multi-channel packed-bed-biofilm reactor (MC-PBR) designed with the aim of solving the problems of pressure drop and oxygen transfer, typically found on this type of bioreactors.Because the removal efficiency of the herbicides was increased when Candida tropicalis was added to the original microbial community isolated, the reactor was inoculated with this enriched community. The operational conditions tested in batch and continuous mode did not affect the removal efficiency of atrazine; however, this was not the case for S-metolachlor. The removal rates and efficiencies showed a notable variation along the MC-PBR operation.

  15. Nuclear reactors for space electric power

    International Nuclear Information System (INIS)

    Buden, D.

    1978-06-01

    The Los Alamos Scientific Laboratory is studying reactor power plants for space applications in the late 1980s and 1990s. The study is concentrating on high-temperature, compact, fast reactors that can be coupled with various radiation shielding systems and thermoelectric, dynamic, or thermionic electric power conversion systems, depending on the mission. Lifetimes of 7 to 10 yr at full power, at converter operating temperatures of 1275 to 1675 0 K, are being studied. The systems are being designed such that no single-failure modes exist that will cause a complete loss of power. In fact, to meet the long lifetimes, highly redundant design features are being emphasized. Questions have been raised about safety since the COSMOS 954 incident. ''Fail-safe'' means to prevent exposure of the population to radioactive material, meeting the environmental guidelines established by the U.S. Government have been and continue to be a necessary requirement for any space reactor program. The major safety feature to prevent prelaunch and launch radioactive material hazards is not operating the reactor before achieving the prescribed orbit. Design features in the reactor ensure that accidental criticality cannot occur. High orbits (above 400 to 500 nautical miles) have sufficient lifetimes to allow radioactive elements to decay to safe levels. The major proposed applications for satellites with reactors in Earth orbit are in geosynchronous orbit (19,400 nautical miles). In missions at geosynchronous orbit, where orbital lifetimes are practically indefinite, the safety considerations are negligible. Orbits below 400 to 500 nautical miles are the ones where a safety issue is involved in case of satellite malfunction. The potential missions, the question of why reactors are being considered as a prime power candidate, reactor features, and safety considerations will be discussed

  16. Health physics aspects of advanced reactor licensing reviews

    Energy Technology Data Exchange (ETDEWEB)

    Hinson, C.S. [Nuclear Regulatory Commission, Washington, DC (United States)

    1995-03-01

    The last Construction Permit to be issued by the U.S. Nuclear Regulatory Commission (NRC) for a U.S. light water reactor (LWR) was granted in the late 1970s. In 1989 the NRC issued 10 CFR Part 52 which is intended to serve as a framework for the licensing of future reactor designs. The NRC is currently reviewing four different future on {open_quotes}next-generation{close_quotes} reactor designs. Two of these designs are classified as evolutionary designs (modified versions of current generation LWRs) and two are advanced designs (reactors incorporating simplified designs and passive means for accident mitigation). These {open_quotes}next-generation{close_quotes} reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four {open_quotes}next-generation{close_quotes} reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four {open_quotes}next-generation{close_quotes} reactor designs currently being reviewed by the NRC.

  17. Reactor Engineering Department annual report (April 1, 1996 - March 31, 1997)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    This report summarizes the research and development activities in the Reactor Engineering Department of JAERI during the fiscal year of 1996 (April 1, 1996 - March 31, 1997). The major Department`s programs promoted in the year are the design activities of advanced reactor system and the development of a high power proton linear accelerator to construct an intense neutron source for innovative neutron science. Other Major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analysis, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC`s fast reactor project were also progressed. The 99 papers are indexed individually. (J.P.N.)

  18. Reactor BR2: Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

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

  19. Naval Health Research Center Command Annual Report Calendar Year 1987 and FY-88

    Science.gov (United States)

    1988-01-01

    information and survey data at the Navy’s overseas laboratories in Cairo, Jakarta, Peru , and Manila were developed. The health status of a number of Navy...computerized data collection techniques for outpatient information and survey data at the Navy’s foreign laboratories in Cairo, Peru , Jarkata, and...negatively associated with tobacco use, "preventive/avoidance" behaviors, age, and ever being overweight . Identifying such factors may help to structure

  20. Constitution and application of reactor make-up system's fault diagnostic Bayesian networks

    International Nuclear Information System (INIS)

    Liang Jie; Cai Qi; Chu Zhuli; Wang Haiping

    2013-01-01

    A fault diagnostic Bayesian network of reactor make-up system was constituted. The system's structure characters, operation rules and experts' experience were combined and an initial net was built. As the fault date sets were learned with the particle swarm optimization based Bayesian network structure, the structure of diagnostic net was completed and used to inference case. The built net can analyze diagnostic probability of every node in the net and afford assistant decision to fault diagnosis. (authors)

  1. Emergency reactor core cooling facility

    International Nuclear Information System (INIS)

    Yoshikawa, Kazuhiro; Kinoshita, Shoichiro; Iwata, Yasutaka.

    1996-01-01

    The present invention provides an emergency reactor core cooling device for a BWR type nuclear power plant. Namely, D/S pit (gas/water separator storage pool) water is used as a water source for the emergency reactor core cooling facility upon occurrence of loss of coolant accidents (LOCA) by introducing the D/S pit water to the emergency reactor core cooling (ECCS) pump. As a result, the function as the ECCS facility can be eliminated from the function of the condensate storage tank which has been used as the ECCS facility. If the function is unnecessary, the level of quality control and that of earthquake resistance of the condensate storage tank can be lowered to a level of ordinary facilities to provide an effect of reducing the cost. On the other hand, since the D/S pit as the alternative water source is usually a facility at high quality control level and earthquake resistant level, there is no problem. The quality of the water in the D/S pit can be maintained constant by elevating pressure of the D/S pit water by a suppression pool cleanup (SPCU) pump to pass it through a filtration desalter thereby purifying the D/S pit water during the plant operation. (I.S.)

  2. Emergency reactor core cooling facility

    Energy Technology Data Exchange (ETDEWEB)

    Yoshikawa, Kazuhiro; Kinoshita, Shoichiro; Iwata, Yasutaka

    1996-11-01

    The present invention provides an emergency reactor core cooling device for a BWR type nuclear power plant. Namely, D/S pit (gas/water separator storage pool) water is used as a water source for the emergency reactor core cooling facility upon occurrence of loss of coolant accidents (LOCA) by introducing the D/S pit water to the emergency reactor core cooling (ECCS) pump. As a result, the function as the ECCS facility can be eliminated from the function of the condensate storage tank which has been used as the ECCS facility. If the function is unnecessary, the level of quality control and that of earthquake resistance of the condensate storage tank can be lowered to a level of ordinary facilities to provide an effect of reducing the cost. On the other hand, since the D/S pit as the alternative water source is usually a facility at high quality control level and earthquake resistant level, there is no problem. The quality of the water in the D/S pit can be maintained constant by elevating pressure of the D/S pit water by a suppression pool cleanup (SPCU) pump to pass it through a filtration desalter thereby purifying the D/S pit water during the plant operation. (I.S.)

  3. Inherently safe light water reactors

    International Nuclear Information System (INIS)

    Ise, Takeharu

    1987-01-01

    Today's large nuclear power reactors of world-wise use have been designed based on the philosophy. It seems that recent less electricity demand rates, higher capital cost and the TMI accident let us acknowledge relative small and simplified nuclear plants with safer features, and that Chernobyl accident in 1983 underlines the needs of intrinsic and passive safety characteristics. In such background, several inherently safe reactor concepts have been presented abroad and domestically. First describing 'Can inherently safe reactors be designed,' then I introduce representative reactor concepts of inherently safe LWRs advocated abroad so far. All of these innovative reactors employ intrinsic and passive features in their design, as follows: (1) PIUS, an acronym for Process Inherent Ultimate Safety, or an integral PWR with passive heat sink and passive shutdown mechanism, advocated by ASEA-ATOM of Sweden. (2) MAP(Minimum Attention Plant), or a self-pressurized, natural circulation integral PWR, promoted by CE Inc. of the U.S. (3) TPS(TRIGA Power System), or a compact PWR with passive heat sink and inherent fuel characteristics of large prompt temperature coefficient, prompted by GA Technologies Inc. of the U.S. (4) PIUS-BWR, or an inherently safe BWR employing passively actuated fluid valves, in competition with PIUS, prompted by ORNL of the U.S. Then, I will describe the domestic trends in Japan and the innovative inherently safe LWRs presented domestically so far. (author)

  4. Suggestion on the safety classification of spent fuel dry storage in China’s pressurized water reactor nuclear power plant

    Science.gov (United States)

    Liu, Ting; Qu, Yunhuan; Meng, De; Zhang, Qiaoer; Lu, Xinhua

    2018-01-01

    China’s spent fuel storage in the pressurized water reactors(PWR) is stored with wet storage way. With the rapid development of nuclear power industry, China’s NPPs(NPPs) will not be able to meet the problem of the production of spent fuel. Currently the world’s major nuclear power countries use dry storage as a way of spent fuel storage, so in recent years, China study on additional spent fuel dry storage system mainly. Part of the PWR NPP is ready to apply for additional spent fuel dry storage system. It also need to safety classificate to spent fuel dry storage facilities in PWR, but there is no standard for safety classification of spent fuel dry storage facilities in China. Because the storage facilities of the spent fuel dry storage are not part of the NPP, the classification standard of China’s NPPs is not applicable. This paper proposes the safety classification suggestion of the spent fuel dry storage for China’s PWR NPP, through to the study on China’s safety classification principles of PWR NPP in “Classification for the items of pressurized water reactor nuclear power plants (GB/T 17569-2013)”, and safety classification about spent fuel dry storage system in NUREG/CR - 6407 in the United States.

  5. Seasonal and spatial variation of atmospheric particulate matter in a developing megacity, the Greater Cairo, Egypt Egipto

    Energy Technology Data Exchange (ETDEWEB)

    Zakey, A.S. [The Abdus Salam International Centre of Theoretical Physics (ICTP) Trieste (Italy)]. E-mail: azakey@ictp.it; Abdel-Wahab, M.M. [Cairo University, Department of Meteorology, Faculty of Science, Cairo (Egypt); Pettersson, J.B.C.; Gatari, M.J.; Hallquist, M. [Department of Chemistry, Atmospheric Science, Goeteborg University, Goeteborg (Sweden)

    2008-04-15

    As an example of a developing megacity the Greater Cairo (GC) area in Egypt has been evaluated with respect to atmospheric particulate matter (PM) and lead (Pb). Particulate matter was collected during 2001-2002 in the two size fractions PM{sub 2}.5 and PM{sub 1}0 at 17 sites representing different activities (industrial, urban, residential and background condition). The PM concentrations were generally high, with yearly average PM{sub 2}.5 and PM{sub 1}0 values of 85 {+-} 12 and 170 {+-} 25 {mu}g/m{sup -}3, respectively. On an annual scale, the high PM levels were due to many sources that included traffic, waste burning and wind blown dust particles emitted from the desert outside GC and the Moqattam hill inside GC. On a seasonal scale, the PM concentrations were highest in the industrial sector during spring, the dusty season, due to the combined effect of dust storm events and anthropogenic emissions over GC. The lowest seasonal concentrations were recorded in the summer season at the background sites. There was a marked increase in PM levels during the period October to December due to burning of waste from harvested rice in the agriculture area in the Nile Delta (north of Cairo). The highest PM{sub 2}.5/PM{sub 1}0 ratio was recorded in the urban sector (0.59) while the lowest ratio was recorded in the residential sector (0.32). The PM{sub 2}.5 and PM{sub 1}0 samples were also analyzed for Pb in order to address the influence of different emission sources. The monthly average concentrations of Pb in both PM{sub 2}.5 (Pb{sub 2}.5) and PM{sub 1}0 (Pb{sub 1}0) varied between 0.4 and 1.8 {+-} {mu}g m{sup -}3 at the non industrial sites. The concentrations were significantly higher in the industrial areas, where concentration up to a maximum of 16 {+-} g m{sup -}3 could be observed. Both the high lead and PM concentrations measured are contributing to local environmental pollution. GC is subjected to high concentrations of particulates most of the year. There is no

  6. Use of radiation technologies in agriculture and medicine

    International Nuclear Information System (INIS)

    Petukhov, V.K.; Chekushin, A.I.

    1994-01-01

    The most important directions of radiation and radiation biological technologies in the agriculture and medicine are elucidated. Kazakstan have possibility for application radiation technologies. There is powerful irradiation plant on the base of WWR-K reactor such could use for medicine materials sterilization. Has been proposed gamma-radiation plant with following technical characteristics: sources activity - 100-120 Ku; effective energy of radiation - 0,6-0,7 MeV; gamma-radiation use coefficient - 35 %; irradiation dose rate - 30-40 R/c; nonuniform irradiation rate - 12 %. Processing tools have being situated to hermetically sealed cylindrical container (height - 2 m; diameter - 1,2 m) and then have being put down under water towards gamma-irradiators

  7. Erythorbic acid promoted formation of CdS QDs in a tube-in-tube micro-channel reactor

    Energy Technology Data Exchange (ETDEWEB)

    Liang, Yan; Tan, Jiawei; Wang, Jiexin; Chen, Jianfeng [State Key Laboratory of Organic–Inorganic Composites, Beijing University of Chemical Technology, Beijing 100029 (China); Research Center of the Ministry of Education for High Gravity Engineering and Technology, Beijing University of Chemical Technology, Beijing 100029 (China); Sun, Baochang, E-mail: sunbc@mail.buct.edu.cn [State Key Laboratory of Organic–Inorganic Composites, Beijing University of Chemical Technology, Beijing 100029 (China); Research Center of the Ministry of Education for High Gravity Engineering and Technology, Beijing University of Chemical Technology, Beijing 100029 (China); Shao, Lei, E-mail: shaol@mail.buct.edu.cn [State Key Laboratory of Organic–Inorganic Composites, Beijing University of Chemical Technology, Beijing 100029 (China); Research Center of the Ministry of Education for High Gravity Engineering and Technology, Beijing University of Chemical Technology, Beijing 100029 (China)

    2014-12-15

    Erythorbic acid assistant synthesis of CdS quantum dots (QDs) was conducted by homogeneous mixing of two continuous liquids in a high-throughput microporous tube-in-tube micro-channel reactor (MTMCR) at room temperature. The effects of the micropore size of the MTMCR, liquid flow rate, mixing time and reactant concentration on the size and size distribution of CdS QDs were investigated. It was found that the size and size distribution of CdS QDs could be tuned in the MTMCR. A combination of erythorbic acid promoted formation technique with the MTMCR may be a promising pathway for controllable mass production of QDs.

  8. Sensitivity and Uncertainty Analysis of Coupled Reactor Physics Problems : Method Development for Multi-Physics in Reactors

    NARCIS (Netherlands)

    Perkó, Z.

    2015-01-01

    This thesis presents novel adjoint and spectral methods for the sensitivity and uncertainty (S&U) analysis of multi-physics problems encountered in the field of reactor physics. The first part focuses on the steady state of reactors and extends the adjoint sensitivity analysis methods well

  9. U.S. Sodium Fast Reactor Codes and Methods: Current Capabilities and Path Forward

    Energy Technology Data Exchange (ETDEWEB)

    Brunett, A. J.; Fanning, T. H.

    2017-06-26

    The United States has extensive experience with the design, construction, and operation of sodium cooled fast reactors (SFRs) over the last six decades. Despite the closure of various facilities, the U.S. continues to dedicate research and development (R&D) efforts to the design of innovative experimental, prototype, and commercial facilities. Accordingly, in support of the rich operating history and ongoing design efforts, the U.S. has been developing and maintaining a series of tools with capabilities that envelope all facets of SFR design and safety analyses. This paper provides an overview of the current U.S. SFR analysis toolset, including codes such as SAS4A/SASSYS-1, MC2-3, SE2-ANL, PERSENT, NUBOW-3D, and LIFE-METAL, as well as the higher-fidelity tools (e.g. PROTEUS) being integrated into the toolset. Current capabilities of the codes are described and key ongoing development efforts are highlighted for some codes.

  10. Preapplication safety evaluation report for the Power Reactor Innovative Small Module (PRISM) liquid-metal reactor. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Donoghue, J.E.; Donohew, J.N.; Golub, G.R.; Kenneally, R.M.; Moore, P.B.; Sands, S.P.; Throm, E.D.; Wetzel, B.A. [Nuclear Regulatory Commission, Washington, DC (United States). Associate Directorate for Advanced Reactors and License Renewal

    1994-02-01

    This preapplication safety evaluation report (PSER) presents the results of the preapplication desip review for die Power Reactor Innovative Small Module (PRISM) liquid-mew (sodium)-cooled reactor, Nuclear Regulatory Commission (NRC) Project No. 674. The PRISM conceptual desip was submitted by the US Department of Energy in accordance with the NRC`s ``Statement of Policy for the Regulation of Advanced Nuclear Power Plants`` (51 Federal Register 24643). This policy provides for the early Commission review and interaction with designers and licensees. The PRISM reactor desip is a small, modular, pool-type, liquid-mew (sodium)-cooled reactor. The standard plant design consists of dim identical power blocks with a total electrical output rating of 1395 MWe- Each power block comprises three reactor modules, each with a thermal rating of 471 MWt. Each module is located in its own below-grade silo and is co to its own intermediate heat transport system and steam generator system. The reactors utilize a metallic-type fuel, a ternary alloy of U-Pu-Zr. The design includes passive reactor shutdown and passive decay heat removal features. The PSER is the NRC`s preliminary evaluation of the safety features in the PRISM design, including the projected research and development programs required to support the design and the proposed testing needs. Because the NRC review was based on a conceptual design, the PSER did not result in an approval of the design. Instead it identified certain key safety issues, provided some guidance on applicable licensing criteria, assessed the adequacy of the preapplicant`s research and development programs, and concluded that no obvious impediments to licensing the PRISM design had been identified.

  11. A world class nuclear research reactor complex for South Africa's nuclear future

    Energy Technology Data Exchange (ETDEWEB)

    Keshaw, Jeetesh [South African Young Nuclear Professional Society, PO Box 9396, Centurion, 0157 (South Africa)

    2008-07-01

    South Africa recently made public its rather ambitious goals pertaining to nuclear energy developments in a Draft Policy and Strategy issued for public comment. Not much attention was given to an important tool for nuclear energy research and development, namely a well equipped and maintained research reactor, which on its own does not do justice to its potential, unless it is fitted with all the ancillaries and human resources as most first world countries have. In South Africa's case it is suggested to establish at least one Nuclear Energy Research and Development Centre at such a research reactor, where almost all nuclear energy related research can be carried out on par with some of the best in the world. The purpose of this work is to propose how this could be done, and motivate why it is important that it be done with great urgency, and with full involvement of young professionals, if South Africa wishes to face up to the challenges mentioned in the Draft Strategy and Policy. (authors)

  12. Reactor feedwater control device

    International Nuclear Information System (INIS)

    Koshi, Yuji.

    1993-01-01

    In the device of the present invention, an excess response is not caused in a reactor feed water system even when voids are fluctuated by using an actual water level signal as a reactor water level signal. That is, a standard water level signal and a reactor water level signal are inputted to a comparator. An adder adds water level difference signal outputted from the comparator and mismatch flow rate signal prepared by multiplying the difference between a main steam flow rate signal and a feed water flow rate signal by a mismatch gain. A feed water controller integrates the added signal and outputs flow rate demand signal. A feed water system receives the flow rate demand signal as input. A water level calculation means is disposed to such a device for calculating an actual water level based on the change of coolant possessing amount of the reactor, and the output thereof is defined as a reactor water level signal. With such procedures, excessive elevation of water level of the reactor can be prevented even upon occurrence of void fluctuation phenomenon or the like in the reactor such as upon sole scram operation. Accordingly, plant shut down caused thereby can be avoided safely. (I.S.)

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

    International Nuclear Information System (INIS)

    Henry, A.F.

    1980-01-01

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

  14. Space reactors, a prospective for the future

    International Nuclear Information System (INIS)

    Wahlquist, E.; Voss, S.S.

    1989-01-01

    The power requirements for future space missions are increasing and alternate power systems will be required to meet these needs. Therefore, in the early 1980's a tri-agency space reactor program, the SP-100, was initiated that is capable of meeting the higher power requirements. To understand the current space reactor program, it is important to review it in the context of past space nuclear programs - including radioisotopes, nuclear rockets and reactors. Initial effort on these programs began in the mid-1950's. Radioisotope generators have been flown on a variety of missions and are continuing to be used. The space reactor and nuclear rocket programs were technically successful but were both terminated in 1973. The current SP-100 program builds on those earlier programs

  15. Reference reactor module for NASA's lunar surface fission power system

    Energy Technology Data Exchange (ETDEWEB)

    Poston, David I [Los Alamos National Laboratory; Kapernick, Richard J [Los Alamos National Laboratory; Dixon, David D [Los Alamos National Laboratory; Werner, James [INL; Qualls, Louis [ORNL; Radel, Ross [SNL

    2009-01-01

    Surface fission power systems on the Moon and Mars may provide the first US application of fission reactor technology in space since 1965. The Affordable Fission Surface Power System (AFSPS) study was completed by NASA/DOE to determine the cost of a modest performance, low-technical risk surface power system. The AFSPS concept is now being further developed within the Fission Surface Power (FSP) Project, which is a near-term technology program to demonstrate system-level TRL-6 by 2013. This paper describes the reference FSP reactor module concept, which is designed to provide a net power of 40 kWe for 8 years on the lunar surface; note, the system has been designed with technologies that are fully compatible with a Martian surface application. The reactor concept uses stainless-steel based. UO{sub 2}-fueled, pumped-NaK fission reactor coupled to free-piston Stirling converters. The reactor shielding approach utilizes both in-situ and launched shielding to keep the dose to astronauts much lower than the natural background radiation on the lunar surface. The ultimate goal of this work is to provide a 'workhorse' power system that NASA can utilize in near-term and future Lunar and Martian mission architectures, with the eventual capability to evolve to very high power, low mass systems, for either surface, deep space, and/or orbital missions.

  16. Research reactors: a tool for science and medicine

    International Nuclear Information System (INIS)

    Ordonez, Juan

    2001-01-01

    The types and uses of research reactors are reviewed. After an analysis of the world situation, the demand of new research reactors of about 20 MW is foreseen. The experience and competitiveness of INVAP S.E. as designer and constructor of research reactors is outlined and the general specifications of the reactors designed by INVAP for Egypt and Australia are given

  17. Curvature Induced by Amyloplast Magnetophoresis in Protonemata of the Moss Ceratodon purpureus1

    Science.gov (United States)

    Kuznetsov, Oleg A.; Schwuchow, Jochen; Sack, Fred D.; Hasenstein, Karl H.

    1999-01-01

    After gravistimulation of Ceratodon purpureus (Hedw.) Brid. protonemata in the dark, amyloplast sedimentation was followed by upward curvature in the wild-type (WT) and downward curvature in the wwr mutant (wrong way response). We used ponderomotive forces induced by high-gradient magnetic fields (HGMF) to simulate the effect of gravity and displace the presumptive statoliths. The field was applied by placing protonemata either between two permanent magnets at the edge of the gap, close to the edge of a magnetized ferromagnetic wedge, or close to a small (<1 mm) permanent magnet. Continuous application of an HGMF in all three configurations resulted in plastid displacement and induced curvature in tip cells of WT and wwr protonemata. WT cells curved toward the HGMF, and wwr cells curved away from the HGMF, comparable to gravitropism. Plastids isolated from protonemal cultures had densities ranging from 1.24 to 1.38 g cm−3. Plastid density was similar for both genotypes, but the mutant contained larger plastids than the WT. The size difference might explain the stronger response of the wwr protonemata to the HGMF. Our data support the plastid-based theory of gravitropic sensing and suggest that HGMF-induced ponderomotive forces can substitute for gravity. PMID:9952461

  18. Qualification of the Taiwan Power Company's pressurized water reactor physics methods using CASMO-4/SIMULATE-3

    Energy Technology Data Exchange (ETDEWEB)

    Lin, Hsien-Chuan, E-mail: linsc@iner.org.tw [Nuclear Engineering Division, Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Yaur, Shung-Jung; Lin, Tzung-Yi; Kuo, Weng-Sheng; Shiue, Jin-Yih; Huang, Yu-Lung [Nuclear Engineering Division, Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China)

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer Studsvik's core management system (CMS) was applied to Taiwan Power Company's pressurized water reactor. Black-Right-Pointing-Pointer Advanced calculation model of shutdown cooling, B-10 depletion and integrated pin exposure were introduced. Black-Right-Pointing-Pointer Core characteristic parameters such as boron letdown, low power physics test (LPPT) predictions, and reaction rate were validated to measurement data. Black-Right-Pointing-Pointer The uncertainty of each item was quantified. - Abstract: This paper presents the validation of Studsvik core management system (CMS) for application to the Maanshan units 1 and 2 reactor core physics analysis (Huang and Yang, 1994). The methodology was validated by demonstrating the ability to obtain accurate and reliable results for various conditions and applications. Core characteristic parameters such as boron letdown, low power physics test (LPPT) predictions, and reaction rate were validated. Analytical results have been compared to measured data and reliability factors of the method have been quantified.

  19. AREVA's nuclear reactors portfolio

    International Nuclear Information System (INIS)

    Marincic, A.

    2009-01-01

    A reasonable assumption for the estimated new build market for the next 25 years is over 340 GWe net. The number of prospect countries is growing almost each day. To address this new build market, AREVA is developing a comprehensive portfolio of reactors intended to meet a wide range of power requirements and of technology choices. The EPR reactor is the flagship of the fleet. Intended for large power requirements, the four first EPRs are being built in Finland, France and China. Other countries and customers are in view, citing just two examples: the Usa where the U.S. EPR has been selected as the technology of choice by several U.S utilities; and the United Kingdom where the Generic Design Acceptance process of the EPR design submitted by AREVA and EDF is well under way, and where there is a strong will to have a plant on line in 2017. For medium power ranges, the AREVA portfolio includes a boiling water reactor and a pressurized water reactor which both offer all of the advantages of an advanced plant design, with excellent safety performance and competitive power generation cost: -) KERENA (1250+ MWe), developed in collaboration with several European utilities, and in particular with Eon; -) ATMEA 1 (1100+ MWe), a 3-loop evolutionary PWR which is being developed by AREVA and Mitsubishi. AREVA is also preparing the future and is deeply involved into Gen IV concepts. It has developed the ANTARES modular HTR reactor (pre-conceptual design completed) and is building upon its vast Sodium Fast Reactor experience to take part into the development of the next prototype. (author)

  20. Linguistic Formalism for Semi-Autonomous Reactor Operation

    International Nuclear Information System (INIS)

    Joo, Sungmoon; Seo, Sang Mun; Suh, Yong-Suk; Park, Cheol

    2017-01-01

    The ultimate goal of our work is to develop a novel, integrated system for semi-autonomous reactor operation by introducing an interfacing language shared by human reactor operators and artificially intelligent service agents (e.g., robots). We envision that human operators and artificially intelligent service agents operate the reactor cooperatively in the future. For example, an artificially intelligent service agent carries out a human reactor operator's command or reports the result of a task commanded by the human reactor operator. This work presents preliminary work towards a unified linguistic formalism for cooperative, semiautonomous reactor operation. Application of the proposed formalism to reactor operator communication domain shows that the formalism effectively captures the syntax and semantics of the domain-specific language defined by the communication protocol.

  1. Reactor core in FBR type reactor

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

    1989-01-01

    In a reactor core in FBR type reactors, a portion of homogenous fuels constituting the homogenous reactor core is replaced with multi-region fuels in which the enrichment degree of fissile materials is lower nearer to the axial center. This enables to condition the composition such that a reactor core having neutron flux distribution either of a homogenous reactor core or a heterogenous reactor core has substantially identical reactivity. Accordingly, in the transfer from the homogenous reactor core to the axially heterogenous reactor core, the average reactivity in the reactor core is substantially equal in each of the cycles. Further, by replacing a portion of the homogenous fuels with a multi-region fuels, thereby increasing the heat generation near the axial center, it is possiable to reduce the linear power output in the regions above and below thereof and, in addition, to improve the thermal margin in the reactor core. (T.M.)

  2. Analysis of log rate noise in Ontario's CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Hinds, H.W. [Dynamic Simulation and Analysis Corp., Deep River, Ontario (Canada); Banica, C.; Arguner, D. [Ontario Power Generation, Ajax, Ontario (Canada); Scharfenberg, R. [Bruce Power, Tiverton, Ontario (Canada)

    2007-07-01

    In the fall of 2003, the operators noticed that in the recently-refurbished Bruce A Shutdown System no. 1 (SDS1) the noise level in Log Rate signals were much larger than before. At the request of the Canadian Nuclear Safety Commission (CNSC), all Canadian CANDU reactors took action to characterize their Log Rate noise. Staff of the Inspection and Maintenance Services division of Ontario Power Generation (OPG) has collected high-speed high-accuracy noise data from nearly all 16 Ontario reactors, either as part of routine measurements before planned outages or as a dedicated noise recording. This paper gives the results of examining a suitable subset of this data, with respect to the characteristics and possible causes of Log Rate noise. The reactor and instrumentation design is different at each station: the locations of the moderator injection nozzles, the location of the ion chambers for each system, and the design of the Log Rate amplifiers. It was found that the Log noise (source of Log Rate noise) was much larger for those ion chambers in the path of the moderator injection nozzles, compared to those which were not in the path. This 'extra' Log noise would then be either attenuated or amplified depending on the transfer function (time constants) of the Log Rate amplifier. It was also observed that most of the Log and Log Rate noise is independent of any other signal measured. Although all CANDU reactors in Ontario have Log and Log Rate noise, the Bruce A SDS1 system has the largest amount of Log Rate noise, because (a) its SDS1 (and RRS) ion chambers are at the top of the reactor in the path of the moderator injection nozzles, and (b) its SDS1 Log Rate amplifiers have the smallest time constants. (author)

  3. Comparative analysis of power conversion cycles optimized for fast reactors of generation IV; Analisis comparativo de ciclos de conversion de potencia optimizados para reactores rapidos de generacion IV

    Energy Technology Data Exchange (ETDEWEB)

    Perez Pichel, G. D.

    2011-07-01

    For the study, which is presented here, has been chosen as the specific parameters of each reactor, which are today the three largest projects within generation IV technology development: ESFR for the reactor's sodium, LEADER for the lead reactor's and finally, GoFastR in the case of reactor gas-cooled.

  4. Reactor engineering department annual report. April 1, 1994 - March 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1994 (April 1, 1994 - March 31, 1995). The major Department`s programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal-hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author).

  5. Reactor Engineering Department annual report. April 1, 1997 - March 31, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Ochiai, Masaaki; Ohnuki, Akira; Ono, Toshihiko [eds.] [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    1998-11-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1997 (April 1, 1997 - March 31, 1998). The major Department`s programs promoted in the year are the achievement of the world-strongest lasing of Free Electron Laser and the verification of the core thermal integrity during design basis events in PWRs. Other Major tasks of the Department are various basic researches on the advanced reactor system design studies, the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

  6. Reactor engineering department annual report. April 1, 1995 - March 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1995 (April 1, 1995 - March 31, 1996). The major Department`s programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermalhydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermalhydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

  7. Light water reactors for the 1990s and beyond - The US program

    International Nuclear Information System (INIS)

    McGoff, D.J.; Giessing, D.F.; Stahlkopf, K.E.; Devine, J.C. Jr.

    1991-01-01

    A national program is underway to ensure the availability and future viability of the Light Water Reactor (LWR) in the United States. Using utility requirements derived from experience with over 100 operating U.S. LWRs, new LWR designs are being developed with improved safety, reliability, maintainability, and compatibility with the environment. A large size LWR standardized plant is to be certified by the Nuclear Regulatory Commission by 1991, and one or more mid-size passive plants by 1995. Supporting programs for improving plant construction and providing protection from severe accidents are also being conducted. Finally, a national effort is underway to extend the operating lives of existing LWRs, thereby providing a substantial contribution to the Nation's electric needs. (author)

  8. Supply of enriched uranium for research reactors

    International Nuclear Information System (INIS)

    Mueller, Hans; Laucht, Juergen

    1996-01-01

    Since the RERTR meeting in 1990 at Newport/USA, NUKEM recommended that the research reactor community agree upon a worldwide unified technical specification for low enriched uranium (LEU) and high enriched uranium (HEU) since there existed numerous specifications both from suppliers/fabricators and research reactors. The target recommended by NUKEM is to arrive at a worldwide unified standard specification in order to facilitate supplies of LEU and HEU to fabricators for fabrication of research reactor fuel elements. In our paper presented at the RERTR meeting at Paris in September 1995, we pointed out that LEU and HEU supplied by the U.S. Department of Energy (DOE) in the past was never 'virgin' material, i.e., it was mixed with reprocessed uranium. Our recommendation was to include this fact in the proposed unified specification. Since the RERTR meeting in 1995 progress on a unified standard specification has been made and we would like to provide more specific information about that in this paper. Furthermore, we will deal with the question whether there is a secure supply of LEU for converted research reactors. We list current and potential suppliers of LEU, noting however, that the DOE has for a number of years been unable to supply any LEU due to production problems. The future availability of LEU of U.S. origin is, of course, essential for those research reactor operators which have converted their reactors from HEU to LEU and which are intending to return spent fuel of U.S. origin to the U.S.A. (author)

  9. Troublesome Thugs or Respectable Rebels? Class, Martyrdom and Cairo’s Revolutionary Ultras

    Directory of Open Access Journals (Sweden)

    Carl Rommel

    2016-05-01

    Full Text Available This ethnographic article explores the politics of Egypt’s Ultras football supporters. The Ultras have frequently been heralded as some of the Egyptian Revolution’s most prominent rebels, in particular, after the Port Said stadium massacre in February 2012, when 72 Ultras members were killed. However, this essay focuses on the earlier phase of violent clashes in central Cairo when the Ultras were highly ambivalent about the ongoing protests. As the article shows, the fan groups were hesitant to join the demonstrations, which at the time were heavily associated with “thuggery” (balṭaga. Only after the death of one of its members did the Ultras whole-heartedly take on their rebellious subjectivity.

  10. Recycle of LWR [Light Water Reactor] actinides to an IFR [Integral Fast Reactor

    International Nuclear Information System (INIS)

    Pierce, R.D.; Ackerman, J.P.; Johnson, G.K.; Mulcahey, T.P.; Poa, D.S.

    1991-01-01

    A large quantity of actinide elements is present in irradiated Light Water Reactor (LWR) fuel that is stored throughout the world. Because of the high fission-to-capture ratio for the transuranium (TRU) elements with the high-energy neutrons in the metal-fueled Integral Fast Reactor (IFR), that reactor can consume these elements effectively. The stored fuel represents a valuable resource for an expanding application of fast power reactors. In addition, removal of the TRU elements from the spent LWR fuel has the potential for increasing the capacity of a high-level waste facility by reducing the heat loads and increasing the margin of safety in meeting licensing requirements. Argonne National Laboratory (ANL) is developing a pyrochemical process, which is compatible with the IFR fuel cycle, for the recovery of TRU elements from LWR fuel. The proposed product is a metallic actinide ingot, which can be introduced into the electrorefining step of the IFR process. The major objective of the LWR fuel recovery process is high TRU element recovery, with decontamination a secondary issue, because fission product removal is accomplished in the IFR process. The extensive pyrochemical processing studies of the 1960s and 1970s provide a basis for the design of possible processes. Two processes were selected for laboratory-scale investigation. One is based on the Salt Transport Process studied at ANL for mixed-oxide fast reactor fuel, and the other is based on the blanket processing studies done for ANL's second Experimental Breeder Reactor (EBR-2). This paper discusses the two processes and is a status report on the experimental studies. 5 refs., 2 figs., 2 tabs

  11. Reactor BR2. Introduction

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2001-04-01

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

  12. RA-0 reactor. New neutronic calculations; Reactor RA-0. Nuevos calculos neutronicos

    Energy Technology Data Exchange (ETDEWEB)

    Rumis, D; Leszczynski, F

    1991-12-31

    An updating of the neutronic calculations performed at the RA-0 reactor, located at the Natural, Physical and Exact Sciences Faculty of Cordoba National University, are herein described. The techniques used for the calculation of a reactor like the RA-0 allows prediction in detail of the flux behaviour in the core`s interior and in the reflector, which will be helpful for experiments design. In particular, the use of WIMSD4 code to make calculations on the reactor implies a novelty in the possible applications of this code to solve the problems that arise in practice. (Author). [Espanol] En este trabajo se actualizan los calculos neutronicos realizados para el reactor RA-0, instalado en la Facultad de Ciencias Exactas, Fisicas y Naturales de la Universidad Nacional de Cordoba. Se describen los calculos realizados hasta la fecha y los resultados obtenidos. Las tecnicas incorporadas al calculo de un reactor como el RA-0 permiten predecir en detalle el comportamiento del flujo en el interior del nucleo y en el reflector, lo que sera una importante ayuda en el diseno de experimentos. En particular, el empleo del codigo WIMSD4 para calculos del reactor completo constituye una novedad en las posibles aplicaciones de ese codigo para resolver problemas que se presentan en la practica. (Autor).

  13. Characterization of the Mamluk painting materials in Cairo, Egypt: El-Ashraf Bersbay Madrasa (826 A.H/ 1423 A.D a case study.

    Directory of Open Access Journals (Sweden)

    prof.Atef Brania

    2010-01-01

    Full Text Available The painting materials in the Islamic monuments in Cairo were variable and distinguished. The accurate identification and characterization of painting materials in an art object or in a paint layer is certainly an important step in the history of art, technology and conservation. The main objective of the present paper is to examine and investigate the different painting materials (pigments, gilding, binding media and painting ground employed in the decorated ceilings of Madrasa of Al-Ashraf Bersbay (Mamluk Jarkasy period. X-ray diffraction (X.R.D., scanning electron microscope SEM (EDAX, light optical microscope (LOM and fourier transform infrared spectroscopy (FTIR, together with determination of physical properties of the support (water content and density and microbiological study, adapted for analysis, investigation and evaluation of the current status. The study revealed the severe damage of painting materials. Gypsum, ultramarine, smalt, prussian blue, red ochre, emerald green, red lead (minium and gold leaves were identified in El-Ashraf Bersbay Madrasa decoration painting.

  14. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, April--June 1977

    Energy Technology Data Exchange (ETDEWEB)

    1977-08-01

    Results from the previously conducted Semiscale Mod-1 ECC injection test series were analyzed. Testing in the LOFT counterpart test series was essentially completed, and the steam generator tube rupture test series was begun. Two tests in the alternate ECC injection test series were conducted which included injection of emergency core coolant into the upper plenum through use of the low pressure injection system. The Loss-of-Fluid Test Program successfully completed nonnuclear Loss-of-Coolant Experiment L1-4. A nuclear test, GC 2-3, in the Power Burst Facility Reactor was performed to evaluate the power oscillation method of determining gap conductance and to determine the effects of initial gap size, fill gas composition, and fuel density on the thermal performance of a light water reactor fuel rod. Additional test results were obtained relative to the behavior of irradiated fuel rods during a fast power increase and during a high power film boiling transient. Fuel model development and verification activities continued for the steady state and transient Fuel Rod Analysis Program, FRAP-S and FRAP-T. A computer code known as RELAP4/MOD7 is being developed to provide best-estimate modeling for reflood during a postulated loss-of-coolant accident (LOCA). A prediction of the fourth test in the boiling water reactor (BWR) Blowdown/Emergency Core Cooling Program was completed and an uncertainty analysis was completed of experimental steady state stable film boiling data for water flowing vertically upward in round tubes. A new multinational cooperative program to study the behavior of entrained liquid in the upper plenum and cross flow in the core during the reflood phase of a pressurized water reactor LOCA was defined.

  15. Reactor power control method and device

    International Nuclear Information System (INIS)

    Fushimi, Atsushi; Ishii, Yoshihiko; Miyamoto, Yoshiyuki; Ishii, Kazuhiko; Kiyoharu, Norihiko; Aizawa, Yuko.

    1997-01-01

    The present invention provides a method and a device suitable to rise the temperature and increase the pressure of the reactor to an aimed pressure in accordance with an aimed value for a reactor water temperature changing rate in the course of rising temperature and increasing pressure of the reactor upon start up of a BWR type power plant. Namely, neutron fluxes in the reactor and the temperature of reactor water are detected respectively. The maximum value among the detected values for the neutron fluxes is detected. The reactor water temperature changing rate is calculated based on the detected values of the reactor water temperature, from which the maximum value of the reactor water temperature changing rate is detected. An aimed value for the neutron flux is calculated in accordance with both detected maximum values and the aimed value of the reactor water temperature changing rate. The position of control rods is adjusted in accordance with the aimed value for the calculated neutron flux. Then, an aimed value for the neutron flux for realizing the aimed value for the reactor water temperature changing rate can be obtained accurately with no influence of the sensitivity of the detected values of the neutron fluxes and the time delay of the reactor water temperature changing rate. (I.S.)

  16. Overview of the Dalat Nuclear Research Reactor

    International Nuclear Information System (INIS)

    Nguyen Nhi Dien; Nguyen Thai Sinh; Luong Ba Vien

    2016-01-01

    The present reactor called Dalat Nuclear Research Reactor (DNRR) has been reconstructed from the former TRIGA Mark II reactor which was designed by General Atomic (GA, San Diego, California, USA), started building in early 1960s, put into operation in 1963 and operated until 1968 at nominal power of 250 kW. In 1975, all fuel elements of the reactor were unloaded and shipped back to the USA. The DNRR is a 500-kW pool-type research reactor using light water as both moderator and coolant. The reactor is used as a neutron source for the purposes of: (1) radioactive isotope production; (2) neutron activation analysis; and (3) research and training

  17. When reactors reach old age

    International Nuclear Information System (INIS)

    Fischetti, M.

    1986-01-01

    While the battle over whether to build new nuclear plants has quieted in recent times, a second struggle is shaping up in the United States as reactors approach a new stage of life: retirement. Four decades into the nuclear power age, questions of how best to dismantle and dispose of a nuclear power plant remain largely unanswered. The debates have been mainly academic until now - although reactors have operated for 25 years, decommissioning retired reactors has simply not been fully planned in this country. But the Shippingport Atomic Power Station in Pennsylvania, the first large-scale power reactor to be retired, is now being decommissioned. The work has rekindled the debates in the light of reality. Outside the United States, decommissioning is also being confronted on a new plane. Virtually all groups involved in decommissioning a reactor in the United States - the utility, the Nuclear Regulatory Commission, the U.S. Department of Energy, the U.S. Environmental Protection Agency, state public service commissions, and citizen organizations - agree that for the most part the technology to dismantle and dispose of a reactor safely is available. They disagree, however, on which technical option is the safest or cheapest and on who should pay for dismantlement. And there are further complications: Which regulations must be complied with. How much radiation exposure for workers and the public is acceptable. Even with answers to these questions, uncertainty about where to dispose of the radioactive waste and about how much residual radiation can be left at a former reactor site plagues the architects of decommissioning. This article discusses these questions

  18. Irradiation behavior of metallic fast reactor fuels

    International Nuclear Information System (INIS)

    Pahl, R.G.; Porter, D.L.; Crawford, D.C.; Walters, L.C.

    1991-01-01

    Metallic fuels were the first fuels chosen for liquid metal cooled fast reactors (LMR's). In the late 1960's world-wide interest turned toward ceramic LMR fuels before the full potential of metallic fuel was realized. However, during the 1970's the performance limitations of metallic fuel were resolved in order to achieve a high plant factor at the Argonne National Laboratory's Experimental Breeder Reactor II. The 1980's spawned renewed interest in metallic fuel when the Integral Fast Reactor (IFR) concept emerged at Argonne National Laboratory. A fuel performance demonstration program was put into place to obtain the data needed for the eventual licensing of metallic fuel. This paper will summarize the results of the irradiation program carried out since 1985

  19. Cermet fuel reactors

    International Nuclear Information System (INIS)

    Cowan, C.L.; Palmer, R.S.; Van Hoomissen, J.E.; Bhattacharyya, S.K.

    1987-01-01

    Cermet fueled nuclear reactors are attractive candidates for high performance space power systems. The cermet fuel consists of tungsten-urania hexagonal fuel blocks characterized by high strength at elevated temperatures, a high thermal conductivity and resultant high thermal shock resistance. The concept evolved in the 1960's with the objective of developing a reactor design which could be used for a wide range of mobile power generation systems including both Brayton and Rankine power conversion cycles. High temperature thermal cycling tests and in-reactor irradiation tests using cermet fuel were carried out by General Electric in the 1960's as part of the 710 Development Program and by Argonne National laboratory in a subsequent activity. Cermet fuel development programs are currently underway at Argonne National laboratory and Pacific Northwest Laboratory as part of the Multi-Megawatt Space Power Program. Key features of the cermet fueled reactor design are 1) the ability to achieve very high coolant exit temperatures, and 2) thermal shock resistance during rapid power changes, and 3) two barriers to fission product release - the cermet matrix and the fuel element cladding. Additionally, there is a potential for achieving a long operating life because of 1) the neutronic insensitivity of the fast-spectrum core to the buildup of fission products and 2) the utilization of a high strength refractory metal matrix and structural materials. These materials also provide resistance against compression forces that potentially might compact and/or reconfigure the core

  20. Nuclear reactor safety research in Idaho

    International Nuclear Information System (INIS)

    Zeile, H.J.

    1983-01-01

    Detailed information about the performance of nuclear reactor systems, and especially about the nuclear fuel, is vital in determining the consequences of a reactor accident. Fission products released from the fuel during accidents are the ultimate safety concern to the general public living in the vicinity of a nuclear reactor plant. Safety research conducted at the Idaho National Engineering Laboratory (INEL) in support of the U.S. Nuclear Regulatory Commission (NRC) has provided the NRC with detailed data relating to most of the postulated nuclear reactor accidents. Engineers and scientists at the INEL are now in the process of gathering data related to the most severe nuclear reactor accident - the core melt accident. This paper describes the focus of the nuclear reactor safety research at the INEL. The key results expected from the severe core damage safety research program are discussed

  1. Pressurized water reactors: the EPR project

    International Nuclear Information System (INIS)

    Py, J.P.; Yvon, M.

    2007-01-01

    EPR (originally 'European pressurized water reactor', and now 'evolutionary power reactor') is a model of reactor initially jointly developed by French and German engineers which fulfills the particular safety specifications of both countries but also the European utility requirements jointly elaborated by the main European power companies under the initiative of Electricite de France (EdF). Today, two EPR-based reactors are under development: one is under construction in Finland and the other, Flamanville 3 (France), received its creation permit decree on April 10, 2007. This article presents, first, the main objectives of the EPR, and then, describes the Flamanville 3 reactor: reactor type and general conditions, core and conditions of operation, primary and secondary circuits with their components, main auxiliary and recovery systems, man-machine interface and instrumentation and control system, confinement and serious accidents, arrangement of buildings. (J.S.)

  2. Design study on sodium-cooled large-scale reactor

    International Nuclear Information System (INIS)

    Shimakawa, Yoshio; Nibe, Nobuaki; Hori, Toru

    2002-05-01

    In Phase 1 of the 'Feasibility Study on Commercialized Fast Reactor Cycle Systems (F/S)', an advanced loop type reactor has been selected as a promising concept of sodium-cooled large-scale reactor, which has a possibility to fulfill the design requirements of the F/S. In Phase 2 of the F/S, it is planed to precede a preliminary conceptual design of a sodium-cooled large-scale reactor based on the design of the advanced loop type reactor. Through the design study, it is intended to construct such a plant concept that can show its attraction and competitiveness as a commercialized reactor. This report summarizes the results of the design study on the sodium-cooled large-scale reactor performed in JFY2001, which is the first year of Phase 2. In the JFY2001 design study, a plant concept has been constructed based on the design of the advanced loop type reactor, and fundamental specifications of main systems and components have been set. Furthermore, critical subjects related to safety, structural integrity, thermal hydraulics, operability, maintainability and economy have been examined and evaluated. As a result of this study, the plant concept of the sodium-cooled large-scale reactor has been constructed, which has a prospect to satisfy the economic goal (construction cost: less than 200,000yens/kWe, etc.) and has a prospect to solve the critical subjects. From now on, reflecting the results of elemental experiments, the preliminary conceptual design of this plant will be preceded toward the selection for narrowing down candidate concepts at the end of Phase 2. (author)

  3. Edge Plasma Physics and Relevant Diagnostics on the CASTOR tokamak

    Czech Academy of Sciences Publication Activity Database

    Stöckel, Jan; Devynck, P.; Gunn, J.; Martines, E.; Bonhomme, G.; Van Oost, G.; Hron, Martin; Ďuran, Ivan; Pánek, Radomír; Stejskal, Pavel; Adámek, Jiří

    2004-01-01

    Roč. 3, - (2004), s. 1-6 ISSN 1433-5581. [First Cairo Conference on Plasma Physics & Applications. Cairo, 11.10.2003-15.10.2003] R&D Projects: GA ČR GA202/03/0786; GA ČR GP202/03/P062 Keywords : tokamak * edge plasma * probe diagnostics * biasing * turbulence * polarization Subject RIV: BL - Plasma and Gas Discharge Physics

  4. Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems

    International Nuclear Information System (INIS)

    Shropshire, D.E.

    2009-01-01

    The Advanced Fuel Cycle Economic Analysis of Symbiotic Light-Water Reactor and Fast Burner Reactor Systems, prepared to support the U.S. Advanced Fuel Cycle Initiative (AFCI) systems analysis, provides a technology-oriented baseline system cost comparison between the open fuel cycle and closed fuel cycle systems. The intent is to understand their overall cost trends, cost sensitivities, and trade-offs. This analysis also improves the AFCI Program's understanding of the cost drivers that will determine nuclear power's cost competitiveness vis-a-vis other baseload generation systems. The common reactor-related costs consist of capital, operating, and decontamination and decommissioning costs. Fuel cycle costs include front-end (pre-irradiation) and back-end (post-irradiation) costs, as well as costs specifically associated with fuel recycling. This analysis reveals that there are large cost uncertainties associated with all the fuel cycle strategies, and that overall systems (reactor plus fuel cycle) using a closed fuel cycle are about 10% more expensive in terms of electricity generation cost than open cycle systems. The study concludes that further U.S. and joint international-based design studies are needed to reduce the cost uncertainties with respect to fast reactor, fuel separation and fabrication, and waste disposition. The results of this work can help provide insight to the cost-related factors and conditions needed to keep nuclear energy (including closed fuel cycles) economically competitive in the U.S. and worldwide. These results may be updated over time based on new cost information, revised assumptions, and feedback received from additional reviews.

  5. Soviet space nuclear reactor incidents - Perception versus reality

    Science.gov (United States)

    Bennett, Gary L.

    1992-01-01

    Since the Soviet Union reportedly began flying nuclear power sources in 1965 it has had four publicly known accidents involving space reactors, two publicly known accidents involving radioisotope power sources and one close call with a space reactor (Cosmos 1900). The reactor accidents, particularly Cosmos 954 and Cosmos 1402, indicated that the Soviets had adopted burnup as their reentry philosophy which is consistent with the U.S. philosophy from the 1960s and 1970s. While quantitative risk analyses have shown that the Soviet accidents have not posed a serious risk to the world's population, concerns still remain about Soviet space nuclear safety practices.

  6. PRISM reactor. An option for plutonium disposition?

    Energy Technology Data Exchange (ETDEWEB)

    Fehlinger, Sebastian; Friess, Friederike; Kuett, Moritz [IANUS, Technische Universitaet Darmstadt (Germany)

    2015-07-01

    The Power Reactor Innovative Small Module (PRISM) is sodium cooled fast reactor model. The energy output depends on the core configuration, however with an energy output of approximately 300 MWe, the PRISM reactor belongs to the class of small modular reactors. Beside using the reactor as a breeder reactor or for the transmutation of nuclear waste, it might also be used as a burner reactor for separated plutonium. This includes for example U.S.-American excess weapon-grade plutonium as well as separated reactor-grade plutonium. Recently, there has been an ongoing discussion in GB to use the PRISM reactor to dispose their excess civilian plutonium. Depending on the task, the core configuration varies slightly. We will present different layouts and the matching MCNP models, these models can then be used to conduct depletion calculations. From these results, analysis of the change in the plutonium isotopics in the spent fuel, the amount of fissioned plutonium, and the possible annual plutonium throughputs is possible.

  7. Prevalence and risk factors of violence among elementary school children in Cairo.

    Science.gov (United States)

    Ez-Elarab, Hanan S; Sabbour, Sahar M; Gadallah, Mohsen A; Asaad, Tarek A

    2007-01-01

    School violence is a growing problem that has received widespread attention. Violent behavior for elementary school children is primarily expressed as physical or verbal aggression. Various factors contribute to violent and aggression by children at homes, schools or individual risk factors. The aim of the present study is to measure the prevalence of violence, risk factors, and different forms among elementary school children, to identify consequence of violent exposure and children with abnormal behavior score. A cross-sectional study was done enrolling a total of 500 elementary students from two mixed schools (private and public) 250 from each in North Cairo Educational Zone. Data collected from students, parents and teachers were: violence behavior, home and family atmosphere, peer relation, exposure to violence at school; being victimized, witness, or initiator, and other risk factors. Standardized questionnaires were used as Achenback Child Behavior checklist, parent and teacher forms of Strength and Difficulty questionnaires (SDQ), and developmental history of child. Monthly grades of students, IQ assessment, physical examination of students were recorded. Prevalence of different forms of violence was higher in public school than private; physical violence 76%, 62% respectively. All forms of violence were higher among boys. Living with a single parent (OR = 2.3), absence of an attachment figure (OR = 13.6), instrumental delivery or cesarean section (OR = 1.9), corporal punishment (OR = 3), violent video games preference (OR = 2.5), exposure to verbal aggression (OR = 3), relations with aggressive peers (OR = 3) were risk factors for violence. Teacher's report of SDQ revealed abnormal score of student's behavior in (32.4%) and (22%) students of public and private schools respectively. The most frequent problems revealed by SDQ among victimized students of both schools was conduct problems (64.7%) in teacher's report and peer relation problems 93.6% in parent

  8. Reactor core and initially loaded reactor core of nuclear reactor

    International Nuclear Information System (INIS)

    Koyama, Jun-ichi; Aoyama, Motoo.

    1989-01-01

    In BWR type reactors, improvement for the reactor shutdown margin is an important characteristic condition togehter with power distribution flattening . However, in the reactor core at high burnup degree, the reactor shutdown margin is different depending on the radial position of the reactor core. That is , the reactor shutdown margin is smaller in the outer peripheral region than in the central region of the reactor core. In view of the above, the reactor core is divided radially into a central region and as outer region. The amount of fissionable material of first fuel assemblies newly loaded in the outer region is made less than the amount of the fissionable material of second fuel assemblies newly loaded in the central region, to thereby improve the reactor shutdown margin in the outer region. Further, the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower portion of the first fuel assemblies is made smaller than the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower region of the second fuel assemblies, to thereby obtain a sufficient thermal margin in the central region. (K.M.)

  9. INAA and chemical analysis of water and sediments sampled in 1996 from the Romanian sector of the Danube river

    International Nuclear Information System (INIS)

    Pantelica, A.; Georgescu, I.I.; Oprica, M.H.I.; Borcia, C.

    1999-01-01

    Water and sediment samples collected during spring 1996 from 20 sampling sites of the Romanian sector of the Danube river and the Black Sea coast were analyzed by instrumental neutron activation analysis (INAA) and by chemical methods to determine major, minor and trace element contents. The concentrations of 43 elements (Ag, Al, As, Au, Ba, Br, Ca, Ce, Cl, Co, Cr, Cu, Cs, Eu, Fe, Ga, Hf, Hg, K, La, Lu, Mg, Mn, Mo, Na, Nd, Ni, Rb, Sb, Sc, Se, Sm, Sr, Ta, Tb, Ti, Th, U, V, W, Yb, Zr, Zn) were investigated by INAA at WWR-S reactor in Bucharest. Chemical methods were used to determine the content of P 2 O 5 and SiO 2 in sediments. For INAA, the water residues and sediment samples were irradiated at the WWR-S reactor in Bucharest at a neutron fluence rate of 2.3·10 12 cm -2 s -1 . As standards, reference materials IAEA-Soil 7 and WTM (sludge from city water treatment, from the Institute of Radioecology and Applied Nuclear Techniques Kosice, Slovakia) as well as chemical compounds of Al, Ca, Mg, V were used. Mono-standard method was applied in the case of Ti and Sr (Cl and Zn as standards, respectively). By chemical methods, the amount of SiO 2 was determined in sediment samples after the treatment with concentrated HCl and residuum dis-aggregation by fusion (melting with a mixture of Na 2 CO 3 and K 2 CO 3 ). Phosphorus was determined by spectrophotometry with ammonium molybdate and by reduction with ascorbic acid. It can be seen that, both for water and sediment samples, the highest contents of Al, Co, Cs, Fe, Rb, and Sb were found at the sites located upstream the Portile de Fier dam: at Turnu Severin (for water) and Orsova (for sediments). Ag, Au, Ni, Yb, Zr were determined only in some of the water samples at the following concentration levels: ng L -1 (Au, Lu), tens of ng L -1 (Ag, Tb, Yb), hundreds of ng L -1 (Ag), μg L -1 (Ni, Zr), tens of μg L -1 (Ni, Ti). From a comparison with results of our previous studies for the Danube bottom sediments, no significant

  10. Reactor core control device

    International Nuclear Information System (INIS)

    Sano, Hiroki

    1998-01-01

    The present invention provides a reactor core control device, in which switching from a manual operation to an automatic operation, and the control for the parameter of an automatic operation device are facilitated. Namely, the hysteresis of the control for the operation parameter by an manual operation input means is stored. The hysteresis of the control for the operation parameter is collected. The state of the reactor core simulated by an operation control to which the collected operation parameters are manually inputted is determined as an input of the reactor core state to the automatic input means. The record of operation upon manual operation is stored as a hysteresis of control for the operation parameter, but the hysteresis information is not only the result of manual operation of the operation parameter. This is results of operation conducted by a skilled operator who judge the state of the reactor core to be optimum. Accordingly, it involves information relevant to the reactor core state. Then, it is considered that the optimum automatic operation is not deviated greatly from the manual operation. (I.S.)

  11. Reactor core performance calculating device

    International Nuclear Information System (INIS)

    Tominaga, Kenji; Bando, Masaru; Sano, Hiroki; Maruyama, Hiromi.

    1995-01-01

    The device of the present invention can calculate a power distribution efficiently at high speed by a plurality of calculation means while taking an amount of the reactor state into consideration. Namely, an input device takes data from a measuring device for the amount of the reactor core state such as a large number of neutron detectors disposed in the reactor core for monitoring the reactor state during operation. An input data distribution device comprises a state recognition section and a data distribution section. The state recognition section recognizes the kind and amount of the inputted data and information of the calculation means. The data distribution section analyzes the characteristic of the inputted data, divides them into a several groups, allocates them to each of the calculation means for the purpose of calculating the reactor core performance efficiently at high speed based on the information from the state recognition section. A plurality of the calculation means calculate power distribution of each of regions based on the allocated inputted data, to determine the power distribution of the entire reactor core. As a result, the reactor core can be evaluated at high accuracy and at high speed irrespective of the whole reactor core or partial region. (I.S.)

  12. Gas-cooled reactors

    International Nuclear Information System (INIS)

    Schulten, R.; Trauger, D.B.

    1976-01-01

    Experience to date with operation of high-temperature gas-cooled reactors has been quite favorable. Despite problems in completion of construction and startup, three high-temperature gas-cooled reactor (HTGR) units have operated well. The Windscale Advanced Gas-Cooled Reactor (AGR) in the United Kingdom has had an excellent operating history, and initial operation of commercial AGRs shows them to be satisfactory. The latter reactors provide direct experience in scale-up from the Windscale experiment to fullscale commercial units. The Colorado Fort St. Vrain 330-MWe prototype helium-cooled HTGR is now in the approach-to-power phase while the 300-MWe Pebble Bed THTR prototype in the Federal Republic of Germany is scheduled for completion of construction by late 1978. THTR will be the first nuclear power plant which uses a dry cooling tower. Fuel reprocessing and refabrication have been developed in the laboratory and are now entering a pilot-plant scale development. Several commercial HTGR power station orders were placed in the U.S. prior to 1975 with similar plans for stations in the FRG. However, the combined effects of inflation, reduced electric power demand, regulatory uncertainties, and pricing problems led to cancellation of the 12 reactors which were in various stages of planning, design, and licensing

  13. Reactor shutdown device

    International Nuclear Information System (INIS)

    Matsumiya, Hirohito; Endo, Hiroshi; Tsuboi, Yasushi.

    1993-01-01

    The present invention concerns a reactor shutdown device capable of suppressing change of a core insertion amount relative to temperature change during normal operation and having a great extension amount due to thermal expansion and high mechanical strength. A control rod main body is contained vertically movably in a guide tube disposed in a reactor core. An extension member extends upward from the upper end of a control rod main body and suspends the control rod main body. A shrinkable member intervenes at a midway of the extension member and is made shrinkable. A temperature sensitive member contains coolants at the inside and surrounds the shrinkable member. Thus, if the temperature of external coolants rises abruptly, the shrinkable member is extended by thermal expansion of the coolants in the temperature sensitive member. Upon usual reactor startup, the coolants in the temperature sensitive member cause no substantial thermal expansion by temperature elevation from a cold shutdown temperature to a rated power operation temperature, and the shrinkable member maintains its original state, so that the control rod main body is not inserted into the reactor core. However, upon abrupt temperature elevation, the control rod main body is inserted into the reactor core. (I.S.)

  14. Tackling the mortality from long-term exposure to outdoor air pollution in megacities: Lessons from the Greater Cairo case study.

    Science.gov (United States)

    Wheida, Ali; Nasser, Amira; El Nazer, Mostafa; Borbon, Agnes; Abo El Ata, Gehad A; Abdel Wahab, Magdy; Alfaro, Stephane C

    2018-01-01

    The poor outdoor air quality in megacities of the developing world and its impact on health is a matter of concern for both the local populations and the decision-makers. The objective of this work is to quantify the mortality attributable to long-term exposure to PM2.5, NO 2 , and O 3 in Greater Cairo (Egypt). We analyze the temporal and spatial variability of the three pollutants concentrations measured at 18 stations of the area. Then, we apply the method recommended by the WHO to estimate the excess mortality. In this assessment, three different shapes (log-linear, linear, and log-log) of the concentration-response functions (CRF) are used. With PM2.5 concentrations varying from 50 to more than 100µg/m 3 in the different sectors of the megacity, the spatial variability of this pollutant is found to be one important cause of uncertainty on the excess mortality associated with it. Also important is the choice of the CRF. With the average (75µg/m 3 ) PM2.5 concentration and the most favorable log-log shape of the CRF, 11% (CI, 9-14%) of the non-accidental mortality in the population older than 30 years can still be attributed to PM2.5, which corresponds to 12520 (CI, 10240-15930) yearly premature deaths. Should the Egyptian legal 70µg/m 3 PM10 limit (corresponding to approximately 37.5µg/m 3 for PM2.5) be met, this number would be reduced to 7970, meaning that 4550 premature deaths could be avoided each year. Except around some industrial or traffic hot spots, NO 2 concentration is found to be below the 40µg/m 3 air quality guideline of the WHO. However, the average concentration (34µg/m 3 ) of this gas exceeds the stricter 10µg/m 3 recommendation of the HRAPIE project and it is thus estimated that from 7850 to 10470 yearly deaths can be attributed to NO 2 . Finally, with the ozone concentration measured at one station only, it is found that, depending on the choice of the CRF, between 2.4% and 8.8% of the mortality due to respiratory diseases can be

  15. Advances in fusion reactor design

    International Nuclear Information System (INIS)

    Baker, C.C.

    1987-01-01

    The author addresses the tokamak as a power reactor. Contrary to popular opinion, there are still a few people that think a tokamak might make a good fusion power reactor. In thinking about advances in fusion reactor design, in the U.S., at least, that generally means advances relevant to the Starfire design. He reviews some of the features of Starfire. Starfire is the last major study done of the tokamak as a reactor in this country. It is now over eight years old in the sense that eight years ago was really the time in which major decisions were made as to its features. Starfire was a tokamak with a major radius of seven meters, about twice the linear dimensions of a machine like TIBER

  16. Technical and economical problems of decommissioning nuclear power plants (NPP) in Russia

    International Nuclear Information System (INIS)

    Vaneev, M.

    2001-01-01

    The introduction per new century has brought to atomic Engineering many new problems. One of them, which has got a serious urgency, we now shall consider. It is a problem of decommissioning NPP in Russia. By 2014 all maintained nowadays NPP in Russian Federation will develop the regular service life. And all of them on idea should be removed from operation. But, as we understand, in today's difficult economic conditions, to it NPP the procedure of prolongation of service life will be applied, and where it is impossible by virtue of the various reasons, the procedure of translation NPP in nuclear - safe condition and in a mode of a long storage under supervision, before acceptance of the decision about a method and way of financing of a decommissioning will be applied. Possible the following variants will be: use platforms of the old NPP for construction new NPP, or using as burial place NPP. The variant of a decommissioning up to a condition 'green grass' is represented unprofitable because of its dearness. The similar decommissioning was carried out in Japan. Was removed from operation research reactor of a type WWR. The expenses for this method of a decommissioning considerably surpass expenses for a method of a burial place NPP basically because of high cost of dismantle and transportation in long-term storehouses of the 1 contour equipment. The most urgent problem of decommissioning NPP, which developed their regular service life - is financing this final stage of a exploitation cycle of the block. I shall remind, that the financing is carried out from uniform fund of decommissioning. The formation of this fund occurs by deduction 1.3 % of cost of the put electric power to the consumers by all maintained NPP of Russia. The expenditure of this fund is carried on time on some tens years. They are spent for 3 basic stages: preparation to decommissioning NPP, long endurance under supervision, dismantle and burial the NPP equipment. Nowadays on faculty NPP MPEI

  17. BWR [boiling-water reactor] and PWR [pressurized-water reactor] off-normal event descriptions

    International Nuclear Information System (INIS)

    1987-11-01

    This document chronicles a total of 87 reactor event descriptions for use by operator licensing examiners in the construction of simulator scenarios. Events are organized into four categories: (1) boiling-water reactor abnormal events; (2) boiling-water reactor emergency events; (3) pressurized-water reactor abnormal events; and (4) pressurized-water reactor emergency events. Each event described includes a cover sheet and a progression of operator actions flow chart. The cover sheet contains the following general information: initial plant state, sequence initiator, important plant parameters, major plant systems affected, tolerance ranges, final plant state, and competencies tested. The progression of operator actions flow chart depicts, in a flow chart manner, the representative sequence(s) of expected immediate and subsequent candidate actions, including communications, that can be observed during the event. These descriptions are intended to provide examiners with a reliable, performance-based source of information from which to design simulator scenarios that will provide a valid test of the candidates' ability to safely and competently perform all licensed duties and responsibilities

  18. Light Water Reactor Sustainability Program, U.S. Efforts in Support of Examinations at Fukushima Daiichi-2017 Evaluations

    Energy Technology Data Exchange (ETDEWEB)

    Farmer, Mitchell T. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-08-01

    Although the accident signatures from each unit at the Fukushima Daiichi Nuclear Power Station (NPS) [Daiichi] differ, much is not known about the end-state of core materials within these units. Some of this uncertainty can be attributed to a lack of information related to cooling system operation and cooling water injection. There is also uncertainty in our understanding of phenomena affecting: a) in-vessel core damage progression during severe accidents in boiling water reactors (BWRs), and b) accident progression after vessel failure (ex-vessel progression) for BWRs and Pressurized Water Reactors (PWRs). These uncertainties arise due to limited full scale prototypic data. Similar to what occurred after the accident at Three Mile Island Unit 2, these Daiichi units offer the international community a means to reduce such uncertainties by obtaining prototypic data from multiple full-scale BWR severe accidents. Information obtained from Daiichi is required to inform Decontamination and Decommissioning activities, improving the ability of the Tokyo Electric Power Company Holdings, Incorporated (TEPCO Holdings) to characterize potential hazards and to ensure the safety of workers involved with cleanup activities. This document, which has been updated to include FY2017 information, summarizes results from U.S. efforts to use information obtained by TEPCO Holdings to enhance the safety of existing and future nuclear power plant designs. This effort, which was initiated in 2014 by the Reactor Safety Technologies Pathway of the Department of Energy Office of Nuclear Energy Light Water Reactor (LWR) Sustainability Program, consists of a group of U.S. experts in LWR safety and plant operations that have identified examination needs and are evaluating TEPCO Holdings information from Daiichi that address these needs. Each year, annual reports include examples demonstrating that significant safety insights are being obtained in the areas of component performance, fission

  19. Population policy at a crossroads. Will world conference signal new directions for U.S.?

    Science.gov (United States)

    Mccarty, L; Sherman, D

    1994-06-01

    In September 1994 in Cairo, at the third population conference hosted by the United Nations, world leaders will be asked to approve a plan that could stabilize the world population at about 8 billion people by the middle of the next century. Participants will consider interrelated issues: population growth, access to family planning, women's empowerment, sustainable development, poverty, consumption, and the environment. This campaign for a more equitable world is likely to continue after Cairo, with the UN-sponsored social summit in Copenhagen and a women's conference in Beijing slated for next year. The Cairo International Conference on Population and Development will require a new approach to sustainability by balancing environmental protection, economic development, and present and future human needs. The United States has only 5% of the world's population, but it uses 25% of the world's commercial energy, produces more garbage and waste than any other country, and generates 21% of all carbon dioxide emissions, which contribute to global warming. Demands for energy, water and food already cannot be met as natural resources are being exhausted at an alarming rate. The fight over water rights to the Colorado River exemplifies the shrinking natural resource base. In contrast to the Reagan-Bush administration, the Clinton administration restored funding to international family planning agencies and endorsed sustainable development. The US birth rate is back at a 2-decade high, while 60% of pregnancies are unintended. US adolescent pregnancy is the highest among industrialized countries, leading to a cycle of poverty and soaring public costs. Government funding for new contraceptive research has been stagnant because of the pressure of right-wing groups, although finally RU-486 became available for clinical trials. The Cairo conference is likely to recognize the US as the leader in global political issues, however, domestic population and consumption issues have

  20. Modeling and performance of the MHTGR [Modular High-Temperature Gas-Cooled Reactor] reactor cavity cooling system

    International Nuclear Information System (INIS)

    Conklin, J.C.

    1990-04-01

    The Reactor Cavity Cooling System (RCCS) of the Modular High- Temperature Gas-Cooled Reactor (MHTGR) proposed by the U.S. Department of Energy is designed to remove the nuclear afterheat passively in the event that neither the heat transport system nor the shutdown cooling circulator subsystem is available. A computer dynamic simulation for the physical and mathematical modeling of and RCCS is described here. Two conclusions can be made form computations performed under the assumption of a uniform reactor vessel temperature. First, the heat transferred across the annulus from the reactor vessel and then to ambient conditions is very dependent on the surface emissivities of the reactor vessel and RCCS panels. These emissivities should be periodically checked to ensure the safety function of the RCCS. Second, the heat transfer from the reactor vessel is reduced by a maximum of 10% by the presence of steam at 1 atm in the reactor cavity annulus for an assumed constant in the transmission of radiant energy across the annulus can be expected to result in an increase in the reactor vessel temperature for the MHTGR. Further investigation of participating radiation media, including small particles, in the reactor cavity annulus is warranted. 26 refs., 7 figs., 1 tab