WorldWideScience

Sample records for cea osiris reactor

  1. OSIRIS Nuclear Reactors and Services Department

    International Nuclear Information System (INIS)

    2008-01-01

    OSIRIS is an experimental reactor with a thermal power of 70 megawatts. It is a light-water reactor, open-core pool type, the principal aim of which is to carry out tests and irradiate the fuel elements and structural materials of nuclear power stations under a high flux of neutrons, and to produce radioisotopes. Located within the French Atomic Energy Commission (CEA) centre at Saclay, it is close to many research teams and inspection laboratories and has a large-scale technological infrastructure. After a presentation of the characteristics of the reactor, the document presents its irradiation positions and experimental conditions (Geometry, Neutron flux, Gamma heating) and its experimental devices (CHOUCA, IRMA, PHAETON, GRIFFONOS, ISABELLE loops, MERCI, IRIS, Instrumentation of the devices, Qualification of the instrumentation). A forth part presents the facilities that are provided to guarantee the quality of the irradiations carried out in the reactor: ISIS reactor model, hot cells, non-destructive inspection means, chemical control of the water, tools for on-line data acquisition and follow-up of experiments, and the calculation and modelling group. A last part is devoted to the hot labs associated to OSIRIS: the LECI, a hot laboratory located on the Saclay site and mainly designed for the study of irradiated materials, and the LECA and STAR facilities, located on the CEA site in Cadarache in the south of France, and which supplement those of Saclay for fuel studies

  2. The use and evolution of the CEA research reactors

    International Nuclear Information System (INIS)

    Rossillon, F.; Chauvez, C.

    1964-01-01

    The authors successively examine the different research reactors in use in the French C.E.A. Nuclear Centres. They trace briefly their histories, describing how they have been used up to the present, and how they have been adapted to changes in programme by means of certain modifications. They also describe the reasons which have led to the elaboration of the project for the new reactor Osiris. Zoe, the oldest reactor in the CEA, has been in service in the Centre de Fontenay-aux-Roses since 1948. It is used mainly for measurements of absorption cross-sections in graphite, and for various short irradiations which do not require high fluxes. The reactor EL 2, in service since 1952, was used for the first studies on gas cooling. It has also been widely used for the production of radioisotopes and for a large number of experiments in the fields of physics, metallurgy and physical chemistry. The ageing of certain elements of the reactor has led to the decision to close it down in the near future The reactor EL 3 has been widely used for experiments in physics and in the investigation of fuels. The possibilities of the reactor in fast neutron irradiations will be considerably improved by the adoption of a new type of core (the 'snow crystal' structure). Triton-I, a 2 MW swimming-pool reactor, is used for the most part for fast neutron and gamma irradiations. The modifications being carried out on it at present should result in an increase in the power of the reactor up to 4 or 5 MW. In a neighbouring compartment is housed Triton-II which is of the same general structure, as Triton-I, but whose maximum power is 100 kW. Triton-II is used solely for studies on shielding. Melusine, a 2 MW swimming-pool reactor, has been in use in the Centre d'Etudes Nucleaires de Grenoble since 1959. It has supported a very high programme concerned mainly with solid state physics, fundamental research into refractory fissile materials and special graphites, and the study of the behaviour of

  3. Osiris reactor descriptive report

    International Nuclear Information System (INIS)

    1976-03-01

    OSIRIS is a swimming pool reactor of 70 MW thermal power. Its main purpose is the irradiation of reactor materials in high neutron flux. A description is given of the air conditioning, ventilation, and radioactive gas removal system. (R.L.)

  4. OSIRIS. Refurbishment and management of ageing effects

    International Nuclear Information System (INIS)

    Joly, C.; Guidez, J.; Contenson, G. de; Marin, J.P.

    1995-01-01

    OSIRIS, one of the French CEA research reactors (Saclay, France), achieved criticality for the first time on July 1966. During the 29 running years OSIRIS was mainly devoted to production and technological irradiations. To satisfy these objectives, OSIRIS is equipped by different test facilities allowing: the long time irradiation of different material including fuel rods, reactor vessel materials, fusion reactor components; the power ramps of fuel rods; the activation analysis; the neutron-radiography of materials and test sections... All the foreseen irradiation programmes will only be possible if safety and high performances of the reactor are guaranteed. That is why a continuous maintenance and improvement programme has taken place during the whole life of the reactor. This paper gives an overview of this programme, mainly about the part conducted during the last years. Details about characteristics of the reactor, history of experiments, maintenance programme, instrumentation and control system, electrotechnical low voltage supply network, decay tanks and water purification system are summarized. The paper focuses on the refurbishment or the replacement of the main components connected to the continuous maintenance programme to guarantee the reliability, the safety and the high performances of the reactor. (J.S.). 2 refs., 8 figs., 2 tabs

  5. Caramel fuel for research reactors: experience acquired in the fabrication, monitoring and irradiation of Osiris core

    International Nuclear Information System (INIS)

    Contenson, Ghislain de; Foulquier, Henri; Trotabas, Maria; Vignesoult, Nicole; Cerles, J.-M.; Delafosse, Jacques.

    1981-06-01

    A plate type nuclear fuel (Caramel fuel) has been developed in France in the framework of the various activities pursued in the design, fabrication and development of nuclear fuels by the CEA. This fuel can be adapted to various different categories of water cooled reactor (power reactors, marine propulsion reactors, urbain heating reactors, research reactors). The successful work conducted in this field led the realization of a complete core and reloads for the high performance research reactor, Osiris, at Saclay. The existing highly enriched U-Al alloy fuel was replaced by a non-proliferating low enrichment (7%) caramel fuel. This new core has been operating successfully since january 1980. A brief description of Caramel and its main advantages is given. The way in which it is fabricated is described together with the quality controls to which it is subjected. The qualification program and the main results deduced from it are also presented. The program used to monitor its in-pile behavior is described. The essential purpose of this program is to ensure the high performance of the fuel under irradiation. The successful operation of Osiris, which terminated 11 irradiation cycles on the 21st of April 1981 confirmed the correctness of the decisions made and the excellent performance that could be achieved with these fuel elements under the severe conditions encountered in a high performance research reactor [fr

  6. The use and evolution of the CEA research reactors; Utilisation et evolution des reacteurs de recherche du C.E.A

    Energy Technology Data Exchange (ETDEWEB)

    Rossillon, F; Chauvez, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The authors successively examine the different research reactors in use in the French C.E.A. Nuclear Centres. They trace briefly their histories, describing how they have been used up to the present, and how they have been adapted to changes in programme by means of certain modifications. They also describe the reasons which have led to the elaboration of the project for the new reactor Osiris. Zoe, the oldest reactor in the CEA, has been in service in the Centre de Fontenay-aux-Roses since 1948. It is used mainly for measurements of absorption cross-sections in graphite, and for various short irradiations which do not require high fluxes. The reactor EL 2, in service since 1952, was used for the first studies on gas cooling. It has also been widely used for the production of radioisotopes and for a large number of experiments in the fields of physics, metallurgy and physical chemistry. The ageing of certain elements of the reactor has led to the decision to close it down in the near future The reactor EL 3 has been widely used for experiments in physics and in the investigation of fuels. The possibilities of the reactor in fast neutron irradiations will be considerably improved by the adoption of a new type of core (the 'snow crystal' structure). Triton-I, a 2 MW swimming-pool reactor, is used for the most part for fast neutron and gamma irradiations. The modifications being carried out on it at present should result in an increase in the power of the reactor up to 4 or 5 MW. In a neighbouring compartment is housed Triton-II which is of the same general structure, as Triton-I, but whose maximum power is 100 kW. Triton-II is used solely for studies on shielding. Melusine, a 2 MW swimming-pool reactor, has been in use in the Centre d'Etudes Nucleaires de Grenoble since 1959. It has supported a very high programme concerned mainly with solid state physics, fundamental research into refractory fissile materials and special graphites, and the study of the behaviour of

  7. Cleansing and dismantling of CEA-Saclay nuclear licensed facilities

    International Nuclear Information System (INIS)

    Jeanjacques, Michel; Delaire, Isabelle; Glevarec, Rebecca; Mandard, Lionel; Martin, Jean-Louis; Serrano, Roger

    2013-01-01

    This summary presents the cleansing and dismantling operations currently realized on the CEA center of Saclay (CEA-Saclay). It was initiated at the beginning of the 2000 years a cleansing and dismantling program of the old Nuclear Licensed Facilities (NLF). Currently this program relates the dismantling operations to the Hot Laboratories (Laboratoires de Haute Activite: LHA) and the old workshops of the Liquid Waste Treatment Plant (Station des Effluents Liquides: STEL), the dismantling preparation of Ulysse reactor and the dismantling studies to the Solid Waste Management Plant (SWMP; Zone de Gestion des Dechets Solides) and the Osiris reactor. (authors)

  8. Simulation and Comparison of the Calorimeters Measuring the Nuclear Heating in the OSIRIS Reactor, with the TRIPOLI-4R Monte-Carlo Code

    International Nuclear Information System (INIS)

    Peron, A.; Malouch, F.; Diop, C.M.

    2013-06-01

    Two calorimeter devices are used in the OSIRIS MTR reactor (CEA-Saclay center) for the nuclear heating measurements. The first one is a fixed five-stage calorimeter device. The second one is an innovative mobile probe called 'CALMOS'. The design of these devices is different (in particular their geometry), implying modifications on the local neutron and photon fluxes and hence on nuclear heating measured values. The measurements performed by the two calorimeter devices cannot directly be compared; this requires perfect irradiation conditions in the reactor core, especially for the core loading and the control element positions. Simulation is here a good help to perform a fully relevant comparison. In this paper, differences between calorimeter devices in terms of nuclear heating and particle fluxes are evaluated using the TRIPOLI-4 Monte-Carlo code. After a description of the OSIRIS reactor and the design of the two calorimeter devices, the nuclear heating calculation scheme used for simulation will be introduced. Different simulations and results will be detailed and analyzed to determine the calorimeter geometry impact on the measured nuclear heating. (authors)

  9. Loss of coolant acident analyses on Osiris research reactor using the RELAP5 code

    International Nuclear Information System (INIS)

    Soares, Humberto Vitor; Costa, Antonella Lombardi; Lima, Claubia Pereira Bezerra; Veloso, Maria Auxiliadora Fortini

    2011-01-01

    RELAP5/MOD 3.3 code is widely used for thermal hydraulic studies of commercial nuclear power plants. However, several current investigations have shown that RELAP5 code can also be applied for thermal hydraulic analysis of nuclear research systems with good predictions. In this paper, a nodalization of the core and the most important components of the primary cooling system of the OSIRIS reactor developed for RELAP5 thermal hydraulic code are presented as well as results of steady state and transient simulations. OSIRIS has thermal power of 70 MW and it is an open pool type research reactor moderated and cooled by water. The OSIRIS reactor characteristics have been used as a base for the development of a model for the Multipurpose Brazilian Reactor (RMB). The aim of the present work is to investigate the behavior of the core during a loss of coolant accident and the possible damage of the fuel elements due an inadequate heat removal. Although the core coolant reached the saturation point due the large break, the fuel element conditions were out of the damage zone. (author)

  10. French experience in design, operation and revamping of nuclear research reactors, in support of advanced reactors development

    International Nuclear Information System (INIS)

    Barre, B.; Bergeonneau, P.; Merchie, F.; Minguet, J.L.; Rousselle, P.

    1996-01-01

    The French nuclear program is strongly based on the R and D work performed in the CEA nuclear research centers and particularly on the various experimental programs carried out in its research reactors in the frame of cooperative actions between the Commissariat a l'Energie Atomique (CEA), Framatome and Electricite de France (EDF). Several types of research reactors have been built by Technicatome and CEA to carry out successfully this considerable R and D work on fuels and materials, among them the socalled Materials Testing Reactors (MTR) SILOE (35 MW) and OSIRIS (70 MW) which are indeed very well suited for technological irradiations. Their simple and flexible design and the large irradiation space available around the core, the SILOE and OSIRIS reactors can be shared by several types of applications such as fuel and material testings for nuclear power plants, radioisotopes production, silicon doping and fundamental research. It is worthwhile recalling that Technicatome and CEA have also built research reactors fully dedicated to safety experimental studies, such as the CABRI, SCARABEE and PHEBUS reactors at Cadarache, and others dedicated to fundamental research such as ORPHEE (14 MW) and the Reacteur a Haut Flux -High Flux Reactor- (RHF 57 MW). This paper will present some of the most significant conceptual and design features of all these reactors as well as the main improvements brought to most of them in the last years. Based on this wide experience, CEA and Technicatome have specially designed for export a new multipurpose research reactor named SIRIUS, with two versions depending on the utilization spectrum and the power range (5 MW to 30 MW). At last, CEA has recently launched the preliminary project study of a new MTR, the Jules Horowitz Reactor, to meet the future needs of fuels and materials irradiations in the next 4 or 5 decades, in support of the French long term nuclear power program. (J.P.N.)

  11. Simulation of power excursions - Osiris reactor; Simulation des excursions de puissance - pile Osiris

    Energy Technology Data Exchange (ETDEWEB)

    Pascouet, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    Following the experimental work accomplished in the U.S.A. on Borax 1 and SPERT 1 and the accident of SL 1, the 'Commissariat a l'Energie Atomique' started a research program about the safety of its own swimming Pool reactors, with regard to power excursions. The first research work led to the design of programmed explosive charges, adapted to the simulation of a power excursion. This report describes the application of these methods to the investigation of Osiris safety. (author) [French] A la suite des essais effectues aux U.S.A. sur BORAX 1 et SPERT 1 et de l'accident survenu a SL 1, le Commissariat a l'Energie Atomique a lance un programme d'etudes sur la surete de ses reacteurs piscines vis-a-vis des excursions de puissance. Les premieres etudes ont abouti A la mise au point de charges programmees capables de simuler une excursion de puissance. On trouvera dans le present rapport l'application de ces methodes a l'etude de la surete d'OSIRIS. (auteur)

  12. Siloe, Osiris, and the future perspective of swimming-pool reactors

    International Nuclear Information System (INIS)

    Chatoux, J.; Denielou, G.; Lerouge, B.

    1964-01-01

    Siloe and Osiris are two new general purpose research reactors of the 'Commissariat a l'energie Atomique'. Siloe, located within the 'Centre d'Etudes Nucleaires' of Grenoble is a swimming pool reactor of the same type as Melusine and Triton. It operates, at a nominal power of 15 MW thermal and has reached the peak power of 20 MW thermal with two thirds of its cooling system working. The fast flux above 1 MeV, which is maximum at the center of the core at 15 MW thermal is 1,2. 10 14 . The core, quite open, is downward cooled. Average specific power is 159 kW/l. Osiris is under construction at Saclay. Designed for 50 MW thermal, this reactor is upward cooled. The fast flux at the center of the core above 1 MeV is calculated to be 2, 5.10 14 . The average designed specific power is 280 kW/l. A fixed zircaloy gamma shield makes a box round the core. Future perspectives open to non-pressurised swimming-pool reactors are examined. Ways are suggested for neutronic; thermal and shielding modifications which make possible further improvements in the performances and economy of these devices. (authors) [fr

  13. Study of the HTGR fission product migration at the Osiris experimental reactor

    International Nuclear Information System (INIS)

    Homme, A. l'; Lucot, M.

    1977-01-01

    A program of study on accidents in HTR reactor operation is presented: blowdown of primary coolant circuit, water inlet into the primary circuit, fuel element overheating by pipe logging or loss of cooling. These studies will be made in Aida irradiation loop in the pool of the Osiris reactor [fr

  14. MTR fuel plate qualification in OSIRIS reactor

    International Nuclear Information System (INIS)

    Sacristan, P.; Boulcourt, P.; Naury, S.; Marchard, L.; Carcreff, H.; Noirot, J.

    2005-01-01

    Qualification of new MTR fuel needs the irradiation in research reactors under representative neutronic, heat flux and thermohydraulic conditions. The experiments are performed in France in the OSIRIS reactor by irradiating MTR full size fuel plates in the IRIS device located in the reactor core. The fuel plates are easily removed from the device during the shutdown of the reactor for performing thickness measurements along the plates by means of a swelling measurement device. Beside the calculation capabilities, the experimental platform includes: the ISIS neutron mock-up for the measurement of neutron flux distribution along the plates; the γ spectrometry for the purpose of measuring the activities of the radionuclides representative of the power and the burnup and to compare with the neutronic calculation. Owing to the experience feedback, a good agreement is observed between calculation and measurement; destructive post irradiation examinations in the LECA facility (Cadarache). New irradiations with the IRIS device and at higher heat flux are under preparation for qualification of MTR fuels. (author)

  15. The Osiris reactor. Descriptive report - Volume 1 - text

    International Nuclear Information System (INIS)

    1969-05-01

    Osiris is a pool type reactor with a 70 MW thermal power. Its main purpose is to irradiate under high flows of neutrons the materials of which future nuclear power stations are made. This report proposes a description of this pool reactor. A first part describes the functional aspects and general characteristics of all installations which are in principle definitely defined (premises, irradiation and experimentation equipment, water circuits, power supply, venting, controls). The second part addresses elements which are likely to be changed, and more particularly the reactor core: fuel elements and controls (uranium and boron load in different fuel element generations, experimental locations within the core), neutron transport aspects (calculation and experiment), and thermal aspects (power generation and removal) of the pile). The third part addresses the operation: operation cycles, stops, exploitation organisation [fr

  16. Hot cells of the Osiris reactor

    International Nuclear Information System (INIS)

    Jourdain, Jean

    1969-10-01

    Hot cells of the Osiris reactor are β and γ type cells. Their main functions are: the extraction of irradiated samples from experimental assemblies (irradiation loops, experimental devices) used to irradiate them, the reinstallation of experimental setups with irradiated samples, the fractioning of unrecoverable experimental devices, and the removal of irradiated samples and active wastes. Each cell is therefore equipped with means for remote handling, for observation and for removal, and a venting. Each cell may also receive additional equipment, notably for the dismantling of experimental setups. This report presents the cell implantation in the reactor, elements to be handled in cells, the path followed by elements to be handled (arrival, departure, conveyors). It describes the cells (capacity and protection, design and construction, external and internal arrangements) and the cell equipment (remote handling devices, windows, lighting, lifting unit, sound system), and the installed electric power. A realisation planning is provided. An appendix indicates the cost of these hot cells

  17. Irradiation devices for fusion reactor materials results obtained from irradiated lithium aluminate at the OSIRIS reactor

    International Nuclear Information System (INIS)

    Lefevre, F.; Thevenot, G.; Rasneur, B.; Botter, F.

    1986-06-01

    Studies about controlled fusion reactor of the Tokamak type require the examination of the radiation effects on the behaviour of various potential materials. Thus, in the first part of this paper, are presented the devices adapted to these materials studies and used in the OSIRIS reactor. In a second part, is described an experiment of irradiation ceramics used as candidates for breeding material and are given the first results

  18. OSIRIS: the first M.T.R. with a new instrumentation and control system based on digital logic of vote

    International Nuclear Information System (INIS)

    Joly, C.; Thiercelin, C.; Corre, J.; Dubois, J.F.; Contenson, G. de.

    1993-01-01

    OSIRIS, one of the french C.E.A. research reactors located at SACLAY, near PARIS, is since 27 years mainly devoted to production and irradiation technologies. To satisfy these objectives, OSIRIS is equipped by different test sections allowing mainly: - the long time irradiation of different materials including fuel rods, reactor vessel materials, fusion reactor components, - the power ramps of fuel rods, the Silicon doping, the radioelements production, the neutronography of materials and test sections. In most of the loops, the nuclear reactor conditions are fully simulated to approach as far as possible the exact behaviour of the materials. Through the new irradiation facilities under development, let's cite the OPERA test section foreseen for the simultaneous irradiation of 32 fuel rods with a maximum length of 2 m. To guarantee the safety and the high performances of the reactor, a continuous maintenance and improvement programme took place during the whole life of the reactor. The paper gives an overview of the part of this programme devoted to the replacement of the instrumentation and control system of the reactor. After 5 years study and development, the on site work took place in the second part of 1992 allowing a reactor start up beginning of 1993. (authors). 10 figs

  19. CEA programme on gas cooled reactors

    International Nuclear Information System (INIS)

    Carre, F.; Fiorini, G.L.; Chapelot, Ph.; Gauthier, J.C.

    2002-01-01

    Future nuclear energy systems studies conducted by the CEA aim at investigating and developing promising technologies for future reactors, fuels and fuel cycles, for nuclear power to play a major part in sustainable energy policies. Reactors and fuel cycles are considered as integral parts of a nuclear system to be optimised as a whole. Major goals assigned to future nuclear energy systems are the following: reinforced economic competitiveness with other electricity generation means, with a special emphasis on reducing the investment cost; enhanced reliability and safety, through an improved management of reactor operation in normal and abnormal plant conditions; minimum production of long lived radioactive waste; resource saving through an effective and flexible use of the available resources of fissile and fertile materials; enhanced resistance to proliferation risks. The three latter goals are essential for the sustainability of nuclear energy in the long term. Additional considerations such as the potentialities for other applications than electricity generation (co-generation, production of hydrogen, sea water desalination) take on an increasing importance. Sustainability goals call for fast neutron spectra (to transmute nuclear waste and to breed fertile fuel) and for recycling actinides from the spent fuel (plutonium and minor actinides). New applications and economic competitiveness call for high temperature technologies (850 deg C), that afford high conversion efficiencies and hence less radioactive waste production and discharged heat. These orientations call for breakthroughs beyond light water reactors. Therefore, as a result of a screening review of candidate technologies, the CEA has selected an innovative concept of high temperature gas cooled reactor with a fast neutron spectrum, robust refractory fuel, direct conversion with a gas turbine, and integrated on-site fuel cycle as a promising system for a sustainable energy development. This objective

  20. Operation of the OSIRIS reactor from the viewpoint of analysis of operator functions

    International Nuclear Information System (INIS)

    Fichet-Clairfontaine, P.Y.; Saint-Jean, T.

    1985-09-01

    This paper presents the results of analyses carried out on site by the Human Factor Study Laboratory in an experimental nuclear plant operated by the Atomic Energy Commissariat - the OSIRIS pool reactor. The analyses of certain tasks are given: work in the reactor hall and an operation of circuit setting performed by the mechanics. This work has thrown light on certain operational guidelines implemented by the operators when carrying out their work [fr

  1. The 'OSIRIS' reactor at Saclay, France and available hot cell facilities. Information sheets

    International Nuclear Information System (INIS)

    Hardt, P. von der; Roettger, H.

    1981-01-01

    Technical information is given on the OSIRIS reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

  2. Nondestructive testing of PWR type fuel rods by eddy currents and metrology in the OSIRIS reactor pool

    International Nuclear Information System (INIS)

    Faure, M.; Marchand, L.

    1985-02-01

    The Saclay Reactor Department has developed a nondestructive test bench, now installed above channel 1 of the OSIRIS reactor. As part of investigations into the dynamics of PWR fuel degradation, a number of fuel rods underwent metrological and eddy current inspection, after irradiation [fr

  3. Utilization of the experimental reactor Osiris for the study and the development of fuels of the fast neutron reactor type

    International Nuclear Information System (INIS)

    Marcon, M.; Faugere, J.L.; Genthon, J.P.; Maillot, R.

    1977-01-01

    Nuclear fuel tests for the fast neutron reactor type have been carried out at the Osiris reactor: thermal study of (U,Pu)O 2 oxide by measurement with thermocouples in the core of the fuel pellet; study of the effects of power cycling on nuclear fuel; study of the mechanical interactions between oxide and cladding by measurement of the cladding deformation during irradiation [fr

  4. R and D on Transmutation at CEA: Recent Results

    International Nuclear Information System (INIS)

    Royet, V.; Delahaye, T.; Lebreton, F.; Picart, S.; Caisso, M.; Gauthe, A.; Ode, D.; Tronche, E.; Bayle, J.P; Warin, D.; Bejaoui, S.; Delage, F.

    2015-01-01

    In the field of minor actinide transmutation in future Generation IV SFR reactor, CEA investigates in priority the recycling of Americium (Am) in the radial blankets located in the outer core area (AmBB: Americium Bearing Blankets). This paper gives an overview of the recent outcomes of the R and D programme carried out at CEA in the different fields of research: from powder elaboration to experimental irradiation. Concerning the powder elaboration, several batches have been produced by the oxalic co-conversion route as well as by the Calcined Resin Microsphere Pelletizing. Different tests have been then performed for the fabrication of pellets according to the current specifications of AmBB. For these two processes, different additional developments of innovative technologies have been achieved well adapted with the processes constraints and hot cell operating. Information on irradiation programmes (MARIOS in HFR and ongoing DIAMINO in Osiris) are presented. The next steps of the programme will then be tackled. (authors)

  5. Calculation to experiment comparison of SPND signals in various nuclear reactor environments

    Energy Technology Data Exchange (ETDEWEB)

    Barbot, Loic; Radulovic, Vladimir; Fourmentel, Damien [CEA, DEN, DER, Instrumentation, Sensors and Dosimetry Laboratory, Cadarache, F-13108 St-Paul-Lez-Durance, (France); Snoj, Luka [Jozef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana, (Slovenia); Tarchalski, Mikolaj [National Centre for Nuclear Research, ulica Andrzeja Soltana 7, 05-400 Otwock (Swierk), (Poland); Dewynter-Marty, Veronique [CEA, DEN, DANS, DRSN, SIREN, LESCI, Saclay, F-91191 Gif sur Yvette, (France); Malouch, Fadhel [CEA, DEN, DANS, DM2S, SERMA, Saclay, F-91191 Gif sur Yvette, (France)

    2015-07-01

    In the perspective of irradiation experiments in the future Jules Horowitz Reactor (JHR), the Instrumentation Sensors and Dosimetry Laboratory of CEA Cadarache (France) is developing a numerical tool for SPND design, simulation and operation. In the frame of the SPND numerical tool qualification, dedicated experiments have been performed both in the Slovenian TRIGA Mark II reactor (JSI) and very recently in the French CEA Saclay OSIRIS reactor, as well as a test of two detectors in the core of the Polish MARIA reactor (NCBJ). A full description of experimental set-ups and neutron-gamma calculations schemes are provided in the first part of the paper. Calculation to experiment comparison of the various SPNDs in the different reactors is thoroughly described and discussed in the second part. Presented comparisons show promising final results. (authors)

  6. First In-Core Measurement Results Obtained with the Innovative Mobile Calorimeter CALMOS inside the OSIRIS Material Testing Reactor

    International Nuclear Information System (INIS)

    Carcreff, Hubert; Salmon, Laurent; Courtaux, Cedric

    2013-06-01

    Nuclear heating rate inside an MTR has to be known in order to design and to run irradiation experiments which have to fulfill target temperature constraints. This measurement is usually carried out by calorimetry [1, 2]. An innovative calorimetric system, CALMOS, has been studied and built in 2011 for the 70 MWth OSIRIS reactor operated by CEA. Thanks to a new calorimetric probe, associated to a specific displacement system, it provides measurements along the fissile height and above the core. The development of the calorimetric probe required the manufacturing and the irradiation of mock-ups in the ex-core area, where nuclear heating rate does not exceed 2 W.g -1 . The calorimeter working mode, the different measurement procedures allowed with such a new probe and main modeling and experimental results have been already presented [3, 4]. In this paper, we present the first results obtained during several measurement campaigns carried out in 2012 and 2013 inside the OSIRIS core with the final device. For the first time, this new experimental measurement system was operated in nominal in-core thermo hydraulic conditions with nominal neutron and gamma fluxes (up to 6 W.g -1 ) in several experimental locations. After a brief presentation of the displacement system specificities, first nuclear heating distributions are presented and discussed. Experimental data were also used to upgrade the Finite Element model of the calorimeter in order to match measured temperatures with calculated ones. This model allowed to estimate a Kc correction factor which takes into account small nonlinearities when the heating rate is deduced from the calibration method. A comparison is made between nuclear heating rates determined from the probe calibration and from the zero method. In addition, an evaluation of the global uncertainty associated to the measurements is detailed. Finally, a global comparison is made with available measurements obtained from previous calorimeters. (authors)

  7. Fast reactor physics at CEA: present studies and future prospects

    International Nuclear Information System (INIS)

    Hammer, P.

    1980-09-01

    This paper aims at giving a general survey of the fast reactor core physics and shielding studies wich are in progress at CEA (1979-1983) in order to solve the neutronic problems related to: - core design optimization, - reactor operation and fuel management, - safety, for the development of fast commercial breeders in France after the SUPER-PHENIX 1 construction is achieved

  8. Final qualification of an industrial wide range neutron instrumentation in the Osiris MTR reactor

    Energy Technology Data Exchange (ETDEWEB)

    Barbot, L.; Normand, S. [CEA, LIST, Laboratoire Capteur et Architectures Electroniques, F-91191 Gif Sur Yvette (France); Pasdeloup, P. [AREVA TA, Controle Commande and Mesures, F-13762 Les Milles (France); Lescop, B. [CEA, INSTN, UEIN, F-91191 Gif Sur Yvette (France)

    2009-07-01

    This work deals with the final qualification of the IRINA in-core neutron flux measurement system in the MTR Osiris reactor. A specific irradiation device has been set up to validate the last changes in the complete system (electronic, transmitting cable and monitor). Experimental results show the IRINA measurement system meet entirely the in-core reactor conditions requirements: a thermal neutron flux from 10{sup 7} n.cm{sup -2}.s{sup -1} up to 10{sup 14} n.cm{sup -2}.s{sup -1} and a temperature of 300 C degrees during a minimum operating time of 1000 hours. (authors)

  9. Management and storage of spent fuel from CEA research reactors

    International Nuclear Information System (INIS)

    Merchie, F.

    1996-01-01

    CEA research reactors and their interim spent fuel storage facilities are described. Long-term solutions for spent fuel storage problems, involving wet storage at PEGASE or dry storage at CASCAD, are outlined in some detail. (author)

  10. Dynamic compensation of the Silver self-powered neutron detector in the ramp program at the OSIRIS reactor

    International Nuclear Information System (INIS)

    Moulin, D.J.

    1994-01-01

    The Silver self-powered neutron detector (SPND) is a common detector used in the ramp program at the OSIRIS reactor. The Silver SPND signal is a reference during steady states, but its response is too slow for monitoring transient tests. In order to compensate for the inherent time delay a mathematical processing method of the Silver SPND signal was developed. Based on a convolution-type resolution of the kinetics equations, a dynamic compensation algorithm can be used for transient conditions as well as steady state conditions. A computer program reconstructs, in real-time, the dynamic neutron flux sensed by the Silver detector from the current measured between the emitter and the collector of the SPND. Although this method decreases slightly the signal-to-noise ratio, it maintains the SPND's characteristics and reduces the response time from about 10 minutes to less than 4 seconds for a step change in flux. This provides for prompt and accurate measurement of fuel rod power during ramp experiments in the OSIRIS reactor. This development makes the Silver SPND very suitable for many on-line monitoring applications

  11. Jules Horowitz Reactor, basic design

    International Nuclear Information System (INIS)

    Bergamaschi, Y.; Bouilloux, Y.; Chantoin, P.; Guigon, B.; Bravo, X.; Germain, C.; Rommens, M.; Tremodeux, P.

    2003-01-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it. It has the ambition to provide the necessary nuclear data and maintain a fission research capacity in Europe after 2010. This capacity should be service-oriented. It will be established in Cadarache. The Jules Horowitz reactor will also: - represent a significant step in term of performances and experimental capabilities, - be designed with a high flexibility, in order to satisfy the current demand from European industry, research and be able to accommodate future requirements, - reach a high level of safety, according to the best current practice. This paper will present the main functionalities and the design options resulting from the 'preliminary design' studies. (authors)

  12. Jules Horowitz reactor, basic design

    International Nuclear Information System (INIS)

    Bergamaschi, Y.; Bouilloux, Y.; Chantoin, P.; Guigon, B.; Bravo, X.; Germain, C.; Rommens, M.; Tremodeux, P.

    2002-01-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it. It has the ambition to provide the necessary nuclear data and maintain a fission research capacity in Europe after 2010. This capacity should be service-oriented. It will be established in Cadarache. The Jules Horowitz reactor will also: represent a significant step in term of performances and experimental capabilities; be designed with a high flexibility, in order to satisfy the current demand from European industry, research and be able to accommodate future requirements; reach a high level of safety, according to the best current practice. This paper will present the main functionalities and the design options resulting from the 'preliminary design' studies. (author)

  13. On-Site Inspection RadioIsotopic Spectroscopy (Osiris) System Development

    International Nuclear Information System (INIS)

    Caffrey, Gus J.; Egger, Ann E.; Krebs, Kenneth M.; Milbrath, B. D.; Jordan, D. V.; Warren, G. A.; Wilmer, N. G.

    2015-01-01

    We have designed and tested hardware and software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy-Osiris-software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,132I. A set of over 100 fission-product spectra was employed for Osiris testing. These spectra were measured, where possible, or generated by modeling. The synthetic test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, Osiris correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.The Osiris gamma-ray spectrometer is a mechanically-cooled, battery-powered ORTEC Transpec-100, chosen to avoid the need for liquid nitrogen during on-site inspections. The spectrometer was used successfully during the recent 2014 CTBT Integrated Field Exercise in Jordan. The spectrometer is controlled and the spectral data analyzed by a Panasonic Toughbook notebook computer. To date, software development has been the main focus of the Osiris project. In FY2016-17, we plan to modify the Osiris hardware, integrate the Osiris software and hardware, and conduct rigorous field tests to ensure that the Osiris system will function correctly during CTBT on-site inspections. The planned development will raise Osiris to technology readiness level TRL-8; transfer the Osiris technology to a commercial manufacturer, and demonstrate Osiris to potential CTBT on-site inspectors.

  14. Licensing procedures and safety criteria for research reactors in France

    International Nuclear Information System (INIS)

    Berry, J.L.; Lerouge, B.

    1983-01-01

    From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon

  15. Licensing procedures and safety criteria for research reactors in France

    Energy Technology Data Exchange (ETDEWEB)

    Berry, J L; Lerouge, B [Centre d' Etudes Nucleaires de Saclay (France)

    1983-08-01

    From the very beginning of the CEA up to now, a great deal of work has been devoted to the development and utilization of research reactors in France for the needs of fundamental and applied research, production of radioisotopes, and training. In recent years, new reactors were commissioned while others were decommissioned. Moreover some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors (Osiris and Isis). This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. At the end, a few considerations are given to the consequences of the Osiris core conversion. Safety of research reactors has been studied in detail and many improvements have been brought due to: implementation of a specific experimental program, and adaptation of safety principles and rules elaborated for power reactors. Research reactors in operation in France have been built within a 22 year period. Meanwhile, safety rules have been improved. Old reactors do not comply with all the new rules but modifications are continuously made: after analysis of incidents, when replacement of equipment has to be carried out, when an important modification (fuel conversion for example) is decided upon.

  16. On-Site Inspection RadioIsotopic Spectroscopy (Osiris) System Development

    Energy Technology Data Exchange (ETDEWEB)

    Caffrey, Gus J. [Idaho National Laboratory, Idaho Falls, ID (United States); Egger, Ann E. [Idaho National Laboratory, Idaho Falls, ID (United States); Krebs, Kenneth M. [Idaho National Laboratory, Idaho Falls, ID (United States); Milbrath, B. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jordan, D. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Warren, G. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wilmer, N. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-09-01

    We have designed and tested hardware and software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy—Osiris—software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,132I. A set of over 100 fission-product spectra was employed for Osiris testing. These spectra were measured, where possible, or generated by modeling. The synthetic test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, Osiris correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.The Osiris gamma-ray spectrometer is a mechanically-cooled, battery-powered ORTEC Transpec-100, chosen to avoid the need for liquid nitrogen during on-site inspections. The spectrometer was used successfully during the recent 2014 CTBT Integrated Field Exercise in Jordan. The spectrometer is controlled and the spectral data analyzed by a Panasonic Toughbook notebook computer. To date, software development has been the main focus of the Osiris project. In FY2016-17, we plan to modify the Osiris hardware, integrate the Osiris software and hardware, and conduct rigorous field tests to ensure that the Osiris system will function correctly during CTBT on-site inspections. The planned development will raise Osiris to technology readiness level TRL-8; transfer the Osiris technology to a commercial manufacturer, and demonstrate Osiris to potential CTBT on-site inspectors.

  17. Online monitoring of the Osiris reactor with the Nucifer neutrino detector

    Science.gov (United States)

    Boireau, G.; Bouvet, L.; Collin, A. P.; Coulloux, G.; Cribier, M.; Deschamp, H.; Durand, V.; Fechner, M.; Fischer, V.; Gaffiot, J.; Gérard Castaing, N.; Granelli, R.; Kato, Y.; Lasserre, T.; Latron, L.; Legou, P.; Letourneau, A.; Lhuillier, D.; Mention, G.; Mueller, Th. A.; Nghiem, T.-A.; Pedrol, N.; Pelzer, J.; Pequignot, M.; Piret, Y.; Prono, G.; Scola, L.; Starzinski, P.; Vivier, M.; Dumonteil, E.; Mancusi, D.; Varignon, C.; Buck, C.; Lindner, M.; Bazoma, J.; Bouvier, S.; Bui, V. M.; Communeau, V.; Cucoanes, A.; Fallot, M.; Gautier, M.; Giot, L.; Guilloux, G.; Lenoir, M.; Martino, J.; Mercier, G.; Milleto, T.; Peuvrel, N.; Porta, A.; Le Quéré, N.; Renard, C.; Rigalleau, L. M.; Roy, D.; Vilajosana, T.; Yermia, F.; Nucifer Collaboration

    2016-06-01

    Originally designed as a new nuclear reactor monitoring device, the Nucifer detector has successfully detected its first neutrinos. We provide the second-shortest baseline measurement of the reactor neutrino flux. The detection of electron antineutrinos emitted in the decay chains of the fission products, combined with reactor core simulations, provides a new tool to assess both the thermal power and the fissile content of the whole nuclear core and could be used by the International Agency for Atomic Energy to enhance the safeguards of civil nuclear reactors. Deployed at only 7.2 m away from the compact Osiris research reactor core (70 MW) operating at the Saclay research center of the French Alternative Energies and Atomic Energy Commission, the experiment also exhibits a well-suited configuration to search for a new short baseline oscillation. We report the first results of the Nucifer experiment, describing the performances of the ˜0.85 m3 detector remotely operating at a shallow depth equivalent to ˜12 m of water and under intense background radiation conditions. Based on 145 (106) days of data with the reactor on (off), leading to the detection of an estimated 40760 ν¯ e , the mean number of detected antineutrinos is 281 ±7 (stat )±18 (syst )ν¯ e/day , in agreement with the prediction of 277 ±23 ν¯ e/day . Because of the large background, no conclusive results on the existence of light sterile neutrinos could be derived, however. As a first societal application we quantify how antineutrinos could be used for the Plutonium Management and Disposition Agreement.

  18. CEA celebrates the jubilee of ZOE reactor

    International Nuclear Information System (INIS)

    Loverini, M.J.

    1998-01-01

    This article reviews the saga of the first French nuclear reactor ZOE. As soon as 1939 Frederic Joliot had an intuition of the possibility of using fissioning nuclei to produce energy. 3 patents describing the concept of a nuclear reactor highlighting the role of natural uranium as fuel, heavy water as moderator, were registered. The only producer in the world of heavy water was a Norwegian firm, a fierce competition with Germany for the control of deuterium broke out. Eventually 185 Kg of heavy water were secretly convoyed in Great-britain. Because of the development of the war, the small scientist team in charge of the project has had to move from France to Great-britain then to Canada. At the end of the war, the 'Commissariat a l'energie atomique' (CEA) was created, its first aim was to design a nuclear reactor as soon as possible. In 1948 the first criticality of ZOE is reached, 6 years later than the team led by Enrico Fermi did in Chicago. In 1976 ZOE was decommissioned and is now a small museum dedicated to nuclear energy. (A.C.)

  19. OSIRIS: an example of gradual conversion

    International Nuclear Information System (INIS)

    Guidez, J.; Beylot, J.; Joly, C.

    1997-01-01

    The conversion of the OSIRIS core from 'Caramel' to silicide forms part of the move towards standardising a well-known fuel, developed in the context of the RERTR programme, and used by the majority of reactors. This standardisation makes it possible to anticipate reduced manufacturing and reprocessing costs in the long term. (author)

  20. Presentation of CEA

    International Nuclear Information System (INIS)

    Graf, J.J.

    1976-01-01

    The organization of the CEA, its missions and means are presented. Its activities in the field of light water reactors, fast neutron reactors and PWR reactors of small and medium power for electricity and/or heat generation are emphasized [fr

  1. Spent fuel scanning using the gamma spectrometry bench at Osiris. Power and burnup determination

    International Nuclear Information System (INIS)

    Cerles, J.-M.; Simonet, Genevieve.

    1976-01-01

    The Saclay Nuclear Research Center is provided with an original gamma spectrometry facility located inside the pool of the Osiris reactor. It is intended for the gamma scanning of fuel elements irradiated in Osiris or elements of any other origin. The principal characteristics of this facility are given. Special emphasis is put on its [fr

  2. Control of the loop IRENE in the experimental reactor OSIRIS: calculation of the departure from nucleate boiling ratio in real time

    International Nuclear Information System (INIS)

    Lucot, Michel; Obin, Norbert.

    1980-10-01

    The loop IRENE is an experimental device to study the behaviour of pressurized light-water fuel pins under neutron flux in the Saclay Nuclear Research Centre reactor OSIRIS. It can take 8 fuel pins and allows irradiations to be carried out under thermodynamic, hydraulic and chemical conditions corresponding to those of a PWR power reactor. A brief outline of the loop specifications is followed by an account of the difficulties raised by operating with saturation temperature at the test channel outlet and it is shown how the microprocessor loop pilots are used to solve these problems [fr

  3. Test devices in Jules Horowitz Reactor dedicated to the material studies in support to the current and future nuclear power plants

    International Nuclear Information System (INIS)

    Colin, C.; Pierre, J.; Blandin, C.; Gonnier, G.; Auclair, M.; Rozenblum, F.

    2015-01-01

    The Jules Horowitz Reactor (JHR) is a tank pool Material Testing Reactor with a maximum thermal power designed at 100 MW. JHR is being built in the CEA Cadarache site and will take over the Osiris reactor whose decommissioning is planned. JHR's design allows a large experimental capability (around 20 experiments at the same time) inside the reactor core, close to the fuel with high fast neutron flux or outside the reactor core, in the reflector with higher thermal neutron flux. A special attention has been put on the improvement of the thermal stability and gradients of the interest zones in samples despite strong gamma heating and on an improvement of the instrumentation devoted to the experiments. This paper presents the JHR and its main experimental devices that include the MICA (Material Irradiation Capsule) device, the CALIPSO (in-Core Advanced Loop for Irradiation in Potassium and Sodium) loop, the OCCITANE (Out-of-Core Capsule for Irradiation Testing of Ageing by Neutrons) rig, and the CLOE (Corrosion Loop Experiment) loop. JHR will play an important role for Gen IV reactors: CEA studies the feasibility of transmutation capsules, of metal liquid irradiation loops for JHR

  4. Last Improvements of the CALMOS Calorimeter Dedicated to Thermal Neutron Flux and Nuclear Heating Measurements inside the OSIRIS Reactor

    Directory of Open Access Journals (Sweden)

    Carcreff H.

    2018-01-01

    Full Text Available Nuclear heating inside an MTR reactor needs to be known in order to design and to run irradiation experiments which have to fulfill target temperature constraints. To improve the nuclear heating knowledge, an innovative calorimetric system CALMOS has been studied, manufactured and tested for the 70MWth OSIRIS reactor operated by CEA. This device is based on a mobile calorimetric probe which can be inserted in any in-core experimental location and can be moved axially from the bottom of the core to 1000 mm above the core mid-plane. Obtained results and advantages brought by the first CALMOS-1 equipment have been already presented. However, some difficulties appeared with this first version. A thermal limitation in cells did not allow to monitor nuclear heating up to the 70 MW nominal power, and some significant discrepancies were observed at high heating rates between results deduced from the calibration and those obtained by the “zero method”. Taking this feedback into account, the new CALMOS-2 calorimeter has been designed both for extending the heating range up to 13W.g-1 and for improving the “zero method” measurement thanks to the implementation of a 4-wires technique. In addition, the new calorimeter has been designed as a real operational measurement system, well suited to characterize and to follow the radiation field evolution throughout the reactor cycle. To meet this requirement, a programmable system associated with a specific software allows automatic complete cell mobility in the core, the data acquisition and the measurements processing. This paper presents the analysis of results collected during the 2015 comprehensive measurement campaign. The 4-wires technique was tested up to around a 4 W.g-1 heating level and allowed to quantify discrepancies between “zero” and calibration methods. Thermal neutron flux and nuclear heating measurements from CALMOS-1 and CALMOS-2 are compared. Thermal neutron flux distributions

  5. Last Improvements of the CALMOS Calorimeter Dedicated to Thermal Neutron Flux and Nuclear Heating Measurements inside the OSIRIS Reactor

    Science.gov (United States)

    Carcreff, H.; Salmon, L.; Lepeltier, V.; Guyot, J. M.; Bouard, E.

    2018-01-01

    Nuclear heating inside an MTR reactor needs to be known in order to design and to run irradiation experiments which have to fulfill target temperature constraints. To improve the nuclear heating knowledge, an innovative calorimetric system CALMOS has been studied, manufactured and tested for the 70MWth OSIRIS reactor operated by CEA. This device is based on a mobile calorimetric probe which can be inserted in any in-core experimental location and can be moved axially from the bottom of the core to 1000 mm above the core mid-plane. Obtained results and advantages brought by the first CALMOS-1 equipment have been already presented. However, some difficulties appeared with this first version. A thermal limitation in cells did not allow to monitor nuclear heating up to the 70 MW nominal power, and some significant discrepancies were observed at high heating rates between results deduced from the calibration and those obtained by the "zero method". Taking this feedback into account, the new CALMOS-2 calorimeter has been designed both for extending the heating range up to 13W.g-1 and for improving the "zero method" measurement thanks to the implementation of a 4-wires technique. In addition, the new calorimeter has been designed as a real operational measurement system, well suited to characterize and to follow the radiation field evolution throughout the reactor cycle. To meet this requirement, a programmable system associated with a specific software allows automatic complete cell mobility in the core, the data acquisition and the measurements processing. This paper presents the analysis of results collected during the 2015 comprehensive measurement campaign. The 4-wires technique was tested up to around a 4 W.g-1 heating level and allowed to quantify discrepancies between "zero" and calibration methods. Thermal neutron flux and nuclear heating measurements from CALMOS-1 and CALMOS-2 are compared. Thermal neutron flux distributions, obtained with the Self-Power Neutron

  6. Gamma spectrometry at OSIRIS. Determination of the power and combustion rate of irradiated fuel elements

    International Nuclear Information System (INIS)

    Destot, M.; Musso, J.F.; Cerles, J.M.

    1975-12-01

    An original gamma spectrometer is available at Saclay near the core of the Osiris reactor. With such a device, it is possible to investigate nuclear fuel elements irradiated at Osiris or originating from power reactors. It is quite possible to build devices based on this principle in nuclear power reactors, more particularly in water reactors. With such a device, it is possible to follow the evolution in space and with time of a large number of fission products, and from there to draw precious conclusions relative to reactor safety (e.g. failed element detection) and to fuel economy (i.e. determination of combustion rate). The general characteristics of the device are given as well as its applications: determination of the mass combustion and of the linear power of an irradiated element. A non-destructive, versatile and fast means of investigation is therefore given by the installation of gamma spectroscopy inside a reactor [fr

  7. First In-Core Simultaneous Measurements of Nuclear Heating and Thermal Neutron Flux Obtained With the Innovative Mobile Calorimeter CALMOS Inside the OSIRIS Reactor

    Science.gov (United States)

    Carcreff, Hubert; Salmon, Laurent; Bubendorff, Jacques; Lepeltier, Valérie

    2016-10-01

    Nuclear heating inside a MTR reactor has to be known in order to design and run irradiation experiments which have to fulfill target temperature constraints. This measurement is usually carried out by calorimetry. The innovative calorimetric system, CALMOS, has been studied and built in 2011 for the 70MWth OSIRIS reactor operated by CEA. Thanks to a new type of calorimetric probe, associated to a specific displacement system, it provides measurements along the fissile height and above the core. Calorimeter working modes, measurement procedures, main modeling and experimental results and expected advantages of this new technique have been already presented in previous papers. However, these first in-core measurements were not performed beyond 6 W · g-1, due to an inside temperature limitation imposed by a safety authority requirement. In this paper, we present the first in-core simultaneous measurements of nuclear heating and conventional thermal neutron flux obtained by the CALMOS device at 70 MW nominal reactor power. For the first time, this experimental system was operated in nominal in-core conditions, with nominal neutron flux up to 2.7 1014 n · cm-2 · s-1 and nuclear heating up to 12 W · g-1. After a brief reminder of the calorimetric cell configuration and displacement system specificities, first nuclear heating distributions at nominal power are presented and discussed. In order to reinforce the heating evaluation, a comparison is made between results obtained by the probe calibration coefficient and the zero methods. Thermal neutron flux evaluation from SPND signal processing required a specific TRIPOLI-4 Monte Carlo calculation which has been performed with the precise CALMOS cell geometry. In addition, the Finite Element model for temperatures map prediction inside the calorimetric cell has been upgraded with recent experimental data obtained up to 12 W · g-1. Finally, the experience feedback led us to improvement perspectives. A second device is

  8. First in-core measurement results obtained with the innovative mobile calorimeter CALMOS inside the OSIRIS material testing reactor

    International Nuclear Information System (INIS)

    Carcreff, Hubert; Salmon, Laurent; Courtaux, Cedric

    2014-01-01

    Nuclear heating rate inside an MTR has to be known in order to design and to run irradiation experiments which have to fulfill target temperature constraints. This measurement is usually carried out by calorimetry. An innovative calorimetric system, CALMOS, has been studied and built in 2011 for the 70 MWth OSIRIS reactor operated by CEA. Thanks to a new calorimetric probe, associated to a specific displacement system, it provides measurements along the fissile height and above the core. Development of the calorimetric probe required manufacturing and irradiation of mock-ups in the ex-core area, where nuclear heating rate does not exceed 2 W.g -1 . The calorimeter working mode, the different measurement procedures, main modeling and ex-core experimental results have been already presented in previous papers. In this paper, we present in-core results obtained from 2011 to 2013 with the final device. For the first time, this new experimental measurement system was operated in several experimental locations, with nominal in-core thermal hydraulic conditions, nominal neutron flux and nuclear heating rate up to 6 W.g -1 (in graphite). After a brief presentation of the displacement system specificities, first nuclear heating distributions are presented and discussed. The Finite Element model of the calorimeter was upgraded in order to match calculated temperatures with measured ones. This 'validated' model allowed to estimate a Kc factor which tends to correct small nonlinearities when heating rate is calculated from the 'calibration method'. A comparison is made between nuclear heating rates determined from 'calibration' and 'zero methods'. In addition, an evaluation of the global uncertainty associated to the measurements is detailed. Finally, a comparison is made with available measurements obtained from previous calorimeters. (authors)

  9. List of reports on reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1985-08-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation of the Federal Ministry for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available from the Society for Reactor Safety (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  10. The CEA and nuclear energy applications

    International Nuclear Information System (INIS)

    1980-01-01

    With PWR reactors, CEA has applied a large part of its activities on steam generators, whilst other technical studies have involved components, maintenance, thermo-hydraulics, safety, materials, instrumentation apparatus and controls. For small light-water reactors, studies carried out have led to development of the Thermos Project: demonstrating the validity of urban heating derived from a pool-type reactor. Other studies have involved fast reactors (manufacture of fissile fuel assemblies, contributions toward the development of the Superphenix project and longer-term studies involving the overall breeder line). Finally, studies on the retreatment of irradiated fuels: aside from the retreatment of irradiated fuel programmes, CEA is pursuing its work on the TOR Project (large-scale pilot for retreatment of fast-neutron fuels) [fr

  11. Press tour Siloe CEA/GRENOBLE; Voyage de presse Siloe CEA/GRENOBLE

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-04-01

    The experimental reactor, Siloe, has been stopped the 23 december 1997. This paper of the Cea Grenoble, presents the historical aspects of this reactor and its missions. It gives then a global description of the stopping and dismantling procedure, with the planning, the financing and the human impacts of the operation. The wastes management is also takes into account. (A.L.B.)

  12. Miniature fission chambers calibration in pulse mode: interlaboratory comparison at the. SCK·CEN BR1 and CEA CALIBAN reactors

    International Nuclear Information System (INIS)

    Lamirand, V.; Geslot, B.; Gregoire, G.; Garnier, D.; Breaud, S.; Mellier, F.; Di-Salvo, J.; Destouches, C.; Blaise, P.; Wagemans, J.; Borms, L.; Malambu, E.; Casoli, P.; Jacquet, X.; Rousseau, G.; Sauvecane, P.

    2013-06-01

    Miniature fission chambers are suited tools for instrumenting experimental reactors, allowing online and in-core neutron measurements of quantities such as fission rates or reactor power. A new set of such detectors was produced by CEA to be used during the next experimental program at the EOLE facility starting in 2013. Some of these detectors will be employed in pulse mode for absolute measurements, thus requiring calibration. The calibration factor is expressed in mass units and thus called 'effective mass'. A calibration campaign was conducted in December 2012 at the SCK.CEN BR1 facility within the framework of the scientific cooperation VEP (VENUS-EOLE-PROTEUS) between SCK.CEN, CEA and PSI. Two actions were conducted in order to improve the calibration method. First a new characterisation of the thermal flux cavity and the MARK3 neutron flux conversion device performed by SCK.CEN allowed using calculated effective cross sections for determining detectors effective masses. Dosimetry irradiations were performed in situ in order to determine the neutron flux level and provide link to the metrological standard. Secondly two fission chambers were also calibrated at the CEA CALIBAN reactor (fast neutron spectrum), using the same method so that the results can be compared with the results obtained at the SCK.CEN. In this paper the calibration method and recent improvements on uncertainty reduction are presented. The results and uncertainties obtained in the two reactors CALIBAN and BR1 are compared and discussed. (authors)

  13. 1999 scientific evaluation at the CEA; L'evaluation scientifique 1999 au CEA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    This report presents a statement of the scientific and technical activity of the French atomic energy commission (CEA) for the year 1999. This evaluation is made by external and independent experts and requires some specific dispositions for the nuclear protection and safety institute (IPSN) and for the direction of military applications (DAM). The report is divided into 4 parts dealing successively with: 1)the CEA, a public research organization (strategy, research programs, new organization of the CEA activities, civil nuclear research, technology research and transfer, defence activities, transfer of knowledge) 2)the scientific evaluation at the CEA (evaluations of the civil applications of the CEA, IPSN, DAM, INSTN (national institute for nuclear sciences and techniques) 3)synthesis of the 1999 scientific and technical evaluation for each operational directions of the CEA (directions of fuel cycle, of nuclear reactors, of advanced technologies, of materials sciences, of life sciences, of military applications, of the nuclear protection and safety institute and of the national institute for nuclear sciences and techniques) 4)the corresponding members of the evaluation and the list of scientific and technical councils and members.

  14. List of reactor safety research reports from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1982-07-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  15. Scientific evaluation at the CEA; Evaluation scientifique au CEA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-11-01

    This report presents a statement of the scientific and technical activity of the French atomic energy commission (CEA) for the year 1998. This evaluation is made by external and independent experts and requires some specific dispositions for the nuclear protection and safety institute (IPSN) and for the direction of military applications (DAM). The report is divided into 5 parts dealing successively with: part 1 - the CEA, a public research organization (civil nuclear research, technology research and transfers, defence activities); the scientific and technical evaluation at the CEA (general framework, evaluation of the IPSN and DAM); part 2 - the scientific and technical councils (directions of fuel cycle, of nuclear reactors, and of advanced technologies); part 3 - the scientific councils (directions of matter and of life sciences); the nuclear protection and safety institute; the direction of military applications; part 4 - the corresponding members of the evaluation; part 5 - the list of scientific and technical councils and members. (J.S.)

  16. 1999 scientific evaluation at the CEA; L'evaluation scientifique 1999 au CEA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    This report presents a statement of the scientific and technical activity of the French atomic energy commission (CEA) for the year 1999. This evaluation is made by external and independent experts and requires some specific dispositions for the nuclear protection and safety institute (IPSN) and for the direction of military applications (DAM). The report is divided into 4 parts dealing successively with: 1)the CEA, a public research organization (strategy, research programs, new organization of the CEA activities, civil nuclear research, technology research and transfer, defence activities, transfer of knowledge) 2)the scientific evaluation at the CEA (evaluations of the civil applications of the CEA, IPSN, DAM, INSTN (national institute for nuclear sciences and techniques) 3)synthesis of the 1999 scientific and technical evaluation for each operational directions of the CEA (directions of fuel cycle, of nuclear reactors, of advanced technologies, of materials sciences, of life sciences, of military applications, of the nuclear protection and safety institute and of the national institute for nuclear sciences and techniques) 4)the corresponding members of the evaluation and the list of scientific and technical councils and members.

  17. CEA and its radioactive wastes

    International Nuclear Information System (INIS)

    Marano, S.

    1999-01-01

    CEA annually produces about 3500 tons of radioactive wastes in its 43 basic nuclear installations. CEA ranks third behind EDF and Cogema. Low-level wastes (A wastes) are sent to ANDRA (national agency for the management of nuclear wastes)whereas medium-level wastes (B wastes) are stored by CEA itself. CEA has checked off its storing places and has set up an installation Cedra to process and store ancient and new nuclear wastes. 3 other installations are planned to operate within 6 years: Agate (Cadarache) will treat liquid effluents, Stella (Saclay) will process liquid wastes that are beta or gamma emitters, and Atena (Marcoule) will treat and store radioactive sodium coming from Phenix reactor and IPSN laboratories. The use of plasma torch for vitrifying wastes is detailed, the management of all the nuclear wastes produced by CEA laboratories and installations is presented. (A.C.)

  18. The Caramel fuel in OSIRIS

    International Nuclear Information System (INIS)

    Cherruau, Francois.

    1980-11-01

    This paper presents the main characteristics of the caramel fuel, a description of OSIRIS transformations that were decided in line with its conversion and the results of its operation since then. The Caramel fuel is made from sintered UO 2 pellets contained in zircaloy clads forming the plates of the fuel assembly reducing the enrichment need to as little as 3 to 10% instead of 93% enriched U/Al in the previous fuel. The first year of experience shows the capacity under a statistic scale of the caramel fuel to fulfil the most severe operation requirements for use in low and medium power research reactors

  19. RERTR programme. French situation in 1996

    International Nuclear Information System (INIS)

    Guidez, J.; Ballagny, A.

    1996-01-01

    This paper summarizes the status of the RERTR Programme in France in 1996. The reactors which are affected by the RERTR Programme are those that consume a considerable amount of fuel. These are the neutron beam reactors Orphee (at Saclay) and RHF (at Grenoble) and the irradiation reactors Osiris (at Saclay) and Siloe (at Grenoble). Plans to construct a new 100 MW, multi-purpose MTR reactor using LEU fuel at the Atomic Research Center at Cadarache are described. Two main topics of fuel research and development are summarized: (1) improving knowledge on the reference silicide fuel, including optimization of the manufacturing process, thermal properties, behavior with cladding failure, etc., and (2) research into low-enriched uranium fuel with a higher U-235 content in order to limit fuel assembly consumption and to improve performance levels. Tests planned in the research and development programme for the silicide fuel are tabulated. The fuel cycle option adopted by the CEA to get rid of spent fuel elements is reprocessing. The 'Caramel' fuel elements consumed in the Osiris reactor until 1995 are currently being reprocessed in CEA facilities at Marcoule. The UAl and UAlx fuel elements irradiated in Siloe and Orphee are currently being reprocessed in the Cogema facilities at Marcoule (Plant UP1). However, the U3Si2 fuel elements irradiated in the Osiris reactor since 1995 will be progressively sent to interim storage dry facilities located at Cadarache. (author)

  20. Gas cooled fast reactor benchmarks for JNC and Cea neutronic tools assessment

    International Nuclear Information System (INIS)

    Rimpault, G.; Sugino, K.; Hayashi, H.

    2005-01-01

    In order to verify the adequacy of JNC and Cea computational tools for the definition of GCFR (gas cooled fast reactor) core characteristics, GCFR neutronic benchmarks have been performed. The benchmarks have been carried out on two different cores: 1) a conventional Gas-Cooled fast Reactor (EGCR) core with pin-type fuel, and 2) an innovative He-cooled Coated-Particle Fuel (CPF) core. Core characteristics being studied include: -) Criticality (Effective multiplication factor or K-effective), -) Instantaneous breeding gain (BG), -) Core Doppler effect, and -) Coolant depressurization reactivity. K-effective and coolant depressurization reactivity at EOEC (End Of Equilibrium Cycle) state were calculated since these values are the most critical characteristics in the core design. In order to check the influence due to the difference of depletion calculation systems, a simple depletion calculation benchmark was performed. Values such as: -) burnup reactivity loss, -) mass balance of heavy metals and fission products (FP) were calculated. Results of the core design characteristics calculated by both JNC and Cea sides agree quite satisfactorily in terms of core conceptual design study. Potential features for improving the GCFR computational tools have been discovered during the course of this benchmark such as the way to calculate accurately the breeding gain. Different ways to improve the accuracy of the calculations have also been identified. In particular, investigation on nuclear data for steel is important for EGCR and for lumped fission products in both cores. The outcome of this benchmark is already satisfactory and will help to design more precisely GCFR cores. (authors)

  1. List of reports on reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1985-01-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l' Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  2. List of reports concerning reactor safety research from BMFT, CEA, EPRI, JSTA, and USNRC

    International Nuclear Information System (INIS)

    1982-12-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these Reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  3. List of reports from the BMFT, CEA, EPRI, JSTA and USNRC concerning reactor safety research

    International Nuclear Information System (INIS)

    1981-09-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special Problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA) the Japan Science and Technology Agency (JSTA) the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Saftety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  4. 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

  5. The CEA-FRAGEMA ramp test programme for the study of the effect of power cycling on PCI at high burn-up

    International Nuclear Information System (INIS)

    Joseph, J.; Atabek, R.; Trotabas, M.

    1983-01-01

    The ramp test programme developed jointly by FRAGEMA and CEA is presented. Today, more than thirty PWR fuel rods have been ramp-tested in experimental reactors SILOE and OSIRIS. Nineteen fuel rods, named 'PRISCA', were base irradiated in BR3 and twelve fuel rods have been refabricated in hot cell by the FABRICE technique. The average fuel burn-up lies between 11 GWd.tU -1 and 46 GWd.tU -1 . In the major cases, the flux profile, during ramp-test, was decentred with respect to the base irradiated flux, and allows to obtain much more information than with a centred flux profile. The failure threshold was established under a set of more than thirty fuel rods of various designs. In particular, the post irradiation examinations allow to locate all rupture locations and thus to define precisely the threshold condition for failure of fuel rods. As an example, the results obtained in the PRISCA 109 experiments are presented. The refabricated fuel rods FABRICE behave identically, with regard to PCI, rather than PRISCA rods. An example of load follow transient in a PWR reactor is presented, and indicates any risk of failure due to PCI. (author)

  6. The CEA contribution to quality control

    International Nuclear Information System (INIS)

    Rapin, M.; Colomer, J.

    1979-01-01

    The Commissariat a l'Energie Atomique has developed original methods and techniques for testing delicate components of the primary circuit of pressure water reactors. These techniques make use of a very wide range of non destructive testing methods: Eddy currents, particularly multiple frequencies, for testing steam generator tubes, gudgeon and other pins focused ultrasonics for testing all the welds of the reactor vessel and its cover plate, mixed welds of steam vessels and generators, low welds of the pressurizer and gudgeon pins from the inside. On site use is effected with specific machines intended either for inspecting the tube bundles of steam generators under the responsibility of INTERCONTROLE Co., or for the complete examination of the reactor vessel by mixed CEA/INTERCONTROLE crews under the responsibility of the CEA. All these operations are subjected to a programme of quality assurance that provides the guaranty of execution complying with the procedures in force [fr

  7. 1999 scientific evaluation at the CEA

    International Nuclear Information System (INIS)

    1999-01-01

    This report presents a statement of the scientific and technical activity of the French atomic energy commission (CEA) for the year 1999. This evaluation is made by external and independent experts and requires some specific dispositions for the nuclear protection and safety institute (IPSN) and for the direction of military applications (DAM). The report is divided into 4 parts dealing successively with: 1)the CEA, a public research organization (strategy, research programs, new organization of the CEA activities, civil nuclear research, technology research and transfer, defence activities, transfer of knowledge) 2)the scientific evaluation at the CEA (evaluations of the civil applications of the CEA, IPSN, DAM, INSTN (national institute for nuclear sciences and techniques) 3)synthesis of the 1999 scientific and technical evaluation for each operational directions of the CEA (directions of fuel cycle, of nuclear reactors, of advanced technologies, of materials sciences, of life sciences, of military applications, of the nuclear protection and safety institute and of the national institute for nuclear sciences and techniques) 4)the corresponding members of the evaluation and the list of scientific and technical councils and members

  8. Behaviour of heavy water in nuclear reactors of the CEA; Comportement de l'eau lourde dans les piles du C.E.A

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J; Dirian, G; Roth, E [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    In the two heavy water reactors of the CEA: Zoe and P-2, we do: A) the supervision of the isotopic composition of the heavy water; B) the supervision of gases released by the decomposition of the heavy water under radiation, and to their recombination; C) periodic analyses of impurities. (M.B.) [French] Dans les deux piles a eau lourde du Commissariat a l'Energie Atomique: Zoe et P 2, nous effectuons: A) la surveillance de la composition isotopique de l'eau lourde; B) la surveillance des gaz degages par la decomposition de l'eau lourde sous radiation, et a leur recombinaison; C) des analyses periodiques d'impuretes. (M.B.)

  9. Deliberated opinion of the Environment Authority concerning the dismantling of the Ulysse reactor (CEA Saclay)

    International Nuclear Information System (INIS)

    2010-01-01

    As the Ulysse reactor of Saclay is about to be dismantled, this report discusses the content of a request made by the CEA to definitely stop and dismantle this reactor. After having recalled the origin of this dismantling project and its regulatory framework, it describes the actual works which are planned, and outlines the main challenges to be faced. It discusses the content of the environmental report or impact study, notably the analysis of the initial condition, the analysis of direct and indirect effects of the project on the environment and health, and of the envisaged measures (waste management, liquid and gaseous effluent management, risk management, radiological exposure of workers in charge of this dismantling, and transports). Recommendations are formulated for a rewriting of the provided documents

  10. List of reports on reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1984-07-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. Requests for reports should be addressed to GRS, Forschungsbetreuung. Contractual points of view have to be considered for the distribitution of the reports. (orig.) [de

  11. Report transparency and nuclear safety 2007 CEA Grenoble; Rapport transparence et securite nucleaire 2007 CEA Grenoble

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of the CEA Center of Grenoble for the year 2007. Since 2002 the Passage project aims to realize the decontamination and the dismantling of old nuclear installations of the CEA Grenoble. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the year 2007 saw two main steps of the Passage project: the decommissioning of the Siloette reactor, a public consultation about the Lama laboratory dismantling. (A.L.B.)

  12. Fast neutron reactor core research at the C.E.A

    International Nuclear Information System (INIS)

    Chaudat, J.-P.

    1978-05-01

    This report covers all physical studies of fast neutron reactors carried out by the C.E.A., to povide basic data (multi-group cross sections) and computer methods which may be used to calculate nuclear power plant neutron properties with the precision required by the project. The approach adopted to establish the basic data used in all core calculations is described in greated detail: choice of a reference procedure for basic mode calculations (CARNAVAL set), choice of particular experimental programs to reduce uncertainties in connection with the formula set, adjustement of cross sections on integral parameters measured on critical experiments. The development of the formula set is closely connected with the project requirements; hence the set is modified with respect to the core characteristics of the power plant studied. Following an explanation of how the CARNAVAL III and IV formula sets -used for PHENIX and SUPER-PHENIX respectively- were derived, current studies for heterogeneous cores are described [fr

  13. Nuclear. In China, the CEA asserts itself as a team leader; Nucleaire: en Chine, le CEA s'impose en meneur de jeu

    Energy Technology Data Exchange (ETDEWEB)

    Dupin, L.

    2011-03-15

    As the French government gave the CEA the responsibility of negotiating the nuclear French-Chinese nuclear strategic partnership, this article outlines the personality of the CEA's chairman, Bernard Bigot, but also the tensions which exist between the two main actors of the French nuclear industry, EDF and Areva, notably about their respective projects of development of a new reactor with China as far as EDF is concerned, and with Japan as far as Areva is concerned. In fact, China is asking France, not to build new reactors but to improve the performance and the safety in the existing ones

  14. Achievement of the level 1 PSA in support to the CEA 2400 MWth gas-cooled fast reactor

    International Nuclear Information System (INIS)

    Balmain, M.; Bassi, C.; Azria, P.

    2012-01-01

    Within Generation IV International Forum, the CEA has developed since 2006 a Level 1 PSA to support the design of the 2400 MWth GFR (Gas-cooled Fast Reactor). A first period, with insights published in 2008, consisted in a model with few initiators representative of medium and high pressure situations, those used for the deterministic design of the Decay Heat Removal (DHR) dedicated loops. In a second period, an iterative work reached the probabilistic targets used for generation III reactors, with prior use of normal loops, and increase of DHR reliability in high pressure conditions. The PSA team covered all the internal initiators, and supported the design of components with instrumentation and control and electrical supplies, and the shutdown operating modes of secondary, tertiary circuits, with possible re-alignment to dedicated DHR loops. Besides, the completed PSA integrated more realistic success criteria than the preliminary model and than the deterministic approach, thanks to CATHARE2 code. In case of loss of Forced Convection, the probability of success of the Natural Convection DHR was assessed by a reliability method for passive systems. The paper underlines the PSA methodology knowledge from the EDF expertise, the improvements co-developed with CEA, and the iteration design-PSA-design. (authors)

  15. System of programs for the management of the common zone of the information processing system APIS working in real time on the reactor OSIRIS

    International Nuclear Information System (INIS)

    Abdel-Shahid, M.A.

    1978-01-01

    The computing system APIS is designed to control the instrumentation of the experimental devices irradiated in the nuclear research reactor OSIRIS (Saclay swimming-pool reactor). OSIRIS runs on cycles of about 25 working days followed by an eight-day shutdown, during which period certain experiments disappear and others are coupled to the system. To obtain the required flexibility the software of the APIS system is made up of a set of application programs, each attached to a switch level and responsible for part of the work of the system. They all work on a memory zone known as ZCU (data zone common to all tasks) which contains all the parameters and arguments defining the system and the processing of connected experiments. This zone must be updated whenever the configuration of the system or experiments is changed. The system APIS for which the management of the ZCU's was made is presented, the general characteristics of the minicomputer MITRA-15 used to handle the ZCU management programs are given and the ZCU of a satellite unit is described in detail. The disadvantages of the present methods used to run the ZCU's are explained, then the method proposed for their automatic management is outlined and its advantages are discussed. The files processed during this work and the programs used for generation, updating and consultation of a ZCU are presented. The list of instructions available at the computer MITRA-15 and that of the subprogram SBRIMT are given in the appendix [fr

  16. Proposal for the CEA/DRN activity on small and medium size reactors research on threshold effects

    International Nuclear Information System (INIS)

    Fiorini, G.L.

    1998-01-01

    The discussion on Small and Medium Size Reactors - SMR is difficult considering the presumptions, justified or not, that affect the debate. Nevertheless, within this context, the CEA/DRN/DER generic objective is the achievement of an exhaustive identification and assessment of the problems that are specific for the SMR. The paper shows the proposals for the activities that are actually under discussion at the CEA/DRN. Among these activities, the research on threshold effects is an essential stage in the assessment of the choices in innovative concepts. This research, as well as the assessment itself, must cover, in an exploratory way, the aspects of operation, safety, economy, fuel cycle, etc. Before starting or, in some cases, continuing this research work, it seems interesting to define a general outline which, by systematising the approach, provides a helpful tool to the designer. The document is a potential starting point (among others) for the discussions. (author)

  17. Utilization of the research reactors for the power reactor control instrumentation development

    International Nuclear Information System (INIS)

    Duchene, J.; Verdant, R.; Gilbert, J.

    1977-01-01

    Studies on characteristics and reliability of control instruments lead to testing with various radiations of various intensities and energy spectra. Osiris and Triton reactors present this great variety of radiations and a flexibility of use better than power reactors [fr

  18. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1990-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  19. List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1991-08-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  20. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1990-02-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  1. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1989-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  2. List of reports in the field of reactor safety research of BMFT, CEA, EPRI, JSTA und USNRC

    International Nuclear Information System (INIS)

    1989-11-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commissariat a l'Engergie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  3. List of reports of BMFT, CEA, EPRI, JSTA and USNRC in the field of reactor safety research

    International Nuclear Information System (INIS)

    1985-04-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of Reactor Safety Research. According to the cooperation of the Bundesminister fuer Forschung und Technologie (BMFT) with the Commisariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electrical Power Research Institute (EPRI) and the United States Nuclear Regulatory Commision, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quaterly. (orig./HP) [de

  4. The research reactors their contribution to the reactors physics

    International Nuclear Information System (INIS)

    Barral, J.C.; Zaetta, A.; Johner, J.; Mathoniere, G.

    2000-01-01

    The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

  5. Scientific evaluation at the CEA

    International Nuclear Information System (INIS)

    1999-01-01

    This report presents a statement of the scientific and technical activity of the French atomic energy commission (CEA) for the year 1998. This evaluation is made by external and independent experts and requires some specific dispositions for the nuclear protection and safety institute (IPSN) and for the direction of military applications (DAM). The report is divided into 5 parts dealing successively with: part 1 - the CEA, a public research organization (civil nuclear research, technology research and transfers, defence activities); the scientific and technical evaluation at the CEA (general framework, evaluation of the IPSN and DAM); part 2 - the scientific and technical councils (directions of fuel cycle, of nuclear reactors, and of advanced technologies); part 3 - the scientific councils (directions of matter and of life sciences); the nuclear protection and safety institute; the direction of military applications; part 4 - the corresponding members of the evaluation; part 5 - the list of scientific and technical councils and members. (J.S.)

  6. Report transparency and nuclear safety 2007 CEA Cadarache; Rapport transparence et securite nucleaire 2007 CEA Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of the CEA Center of Cadarache for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the report discusses the beginning of the RJH reactor construction, the fourth generation reactors research programs, the implementing of la Rotonde the new radioactive wastes management installation, the renovation of the LECA. (A.L.B.)

  7. First in-core simultaneous measurements of nuclear heating and thermal neutron flux obtained with the innovative mobile calorimeter CALMOS inside the OSIRIS reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lepeltier, Valerie; Bubendorff, Jacques; Carcreff, Hubert [Nuclear studies and reactor irradiation Service, CEA Saclay 91191 Gif sur Yvette (France); Salmon, Laurent [Thermalhydraulics and Fluid Mechanics Section, CEA Saclay 91191 Gif sur Yvette, (France)

    2015-07-01

    Nuclear heating inside a MTR reactor has to be known in order to design and to run irradiation experiments which have to fulfill target temperature constraints. This measurement is usually carried out by calorimetry. The innovative calorimetric system, CALMOS, has been studied and built in 2011 for the 70 MWth OSIRIS reactor operated by CEA. Thanks to a new type of calorimetric probe, associated to a specific displacement system, it provides measurements along the fissile height and above the core. This development required preliminary modelling and irradiation of mock-ups of the calorimetric probe in the ex-core area, where nuclear heating rate does not exceed 2 W.g{sup -1}. The calorimeter working modes, the different measurement procedures allowed with such a new probe, the main modeling and experimental results and expected advantages of this new technique have been already presented. However, these first in-core measurements were not performed beyond 6 W.g{sup -1}, due to an inside temperature limitation imposed by a safety authority requirement. In this paper, we present the first in-core simultaneous measurements of nuclear heating and conventional thermal neutron flux obtained by the CALMOS device at the 70 MW nominal reactor power. For the first time, this experimental system was operated in nominal in-core conditions, with nominal neutron flux up to 2.7 10{sup 14} n.cm{sup -2}.s{sup -1} and nuclear heating up to 12 W.g{sup -1}. A comprehensive measurement campaign carried out from 2013 to 2015 inside all accessible irradiation locations of the core, allowed to qualify definitively this new device, not only in terms of measurement ability but also in terms of reliability. After a brief reminder of the calorimetric cell configuration and displacement system specificities, first nuclear heating distributions at nominal power are presented and discussed. In order to reinforce the heating evaluation, a systematic comparison is made between results obtained by

  8. In-pile gamma spectrometry and irradiation control at Osiris

    International Nuclear Information System (INIS)

    Farny, G.; Destot, M.; Corre, J.; Texier, D.; Faugere, J.L.; Mouchnino, M.

    1975-01-01

    A new gamma spectrometry facility is available near Osiris reactor core, at Saclay. This device enables nuclear fuels to be examined in loops or capsules all along their irradiation, a few minutes being sufficient to transfer the fuel from the irradiation place to the measurement bench. So, spacelike and timelike history of a lot of fission products, especially short-lived radionuclides, can be observed. Using such in-pile spectrometry device, of original design, allows to avoid radioactive decay corrections and the risks of any information less. Performance of the device is given together with some preliminary results and their interpretation [fr

  9. The CEA-industrie Group. Report for 1986

    International Nuclear Information System (INIS)

    1987-01-01

    From the end of 1983, the whole affiliates and participations of CEA are hept by CEA-industry. The group activity is principally in the nuclear field. Cogema and the whole fuel cycle, construction, maintenance, improvement of nuclear power plants, research reactors and naval propulsion boilers and the sector Power plants and nuclear services (Framatome, Technicatome, Intercontrole, Stmi, principally). A non-nuclear sector comes from new techniques or activities developed for the nuclear needs: computer science (CISI), biomedical field (ORIS-industrie), different activities such as ultrafiltration or robotics-productics [fr

  10. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1987-05-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Federal Minister for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  11. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC

    International Nuclear Information System (INIS)

    1987-02-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Federal Minister for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  12. Thermal-hydraulic investigations on the CEA-ENEA DEMO relevant helium cooled poloidal blanket

    International Nuclear Information System (INIS)

    Dell'Orco, G.; Polazzi, G.; Vallette, F.; Proust, E.; Eid, M.

    1994-01-01

    The CEA-ENEA design of an Helium Cooled Solid Breeder Blanket (HCSBB) for the DEMO reactor, with a breeder in tube (BIT) poloidal arrangement, is based on the use of lithium ceramic pellets, the ENEA γ-LiAlO 2 or the CEA Li 2 ZrO 3 . Due to the geometry of the DEMO reactor plasma chamber, these breeder bundles are adapted to the Vacuum Vessel with a strong poloidal curvature. This curvature influences the thermal-hydraulic behaviour of the coolant flowing inside the bundle. The paper presents the CEA-ENEA first results of the experimental and theoretical programme, aiming at optimizing the breeder module thermal hydraulic design. (author) 6 refs.; 7 figs.; 1 tab

  13. The OSIRIS-REx Laser Altimeter (OLA) Investigation and Instrument

    Science.gov (United States)

    Daly, M. G.; Barnouin, O. S.; Dickinson, C.; Seabrook, J.; Johnson, C. L.; Cunningham, G.; Haltigin, T.; Gaudreau, D.; Brunet, C.; Aslam, I.; Taylor, A.; Bierhaus, E. B.; Boynton, W.; Nolan, M.; Lauretta, D. S.

    2017-10-01

    The Canadian Space Agency (CSA) has contributed to the Origins Spectral Interpretation Resource Identification Security-Regolith Explorer (OSIRIS-REx) spacecraft the OSIRIS-REx Laser Altimeter (OLA). The OSIRIS-REx mission will sample asteroid 101955 Bennu, the first B-type asteroid to be visited by a spacecraft. Bennu is thought to be primitive, carbonaceous, and spectrally most closely related to CI and/or CM meteorites. As a scanning laser altimeter, the OLA instrument will measure the range between the OSIRIS-REx spacecraft and the surface of Bennu to produce digital terrain maps of unprecedented spatial scales for a planetary mission. The digital terrain maps produced will measure ˜7 cm per pixel globally, and ˜3 cm per pixel at specific sample sites. In addition, OLA data will be used to constrain and refine the spacecraft trajectories. Global maps and highly accurate spacecraft trajectory estimates are critical to infer the internal structure of the asteroid. The global and regional maps also are key to gain new insights into the surface processes acting across Bennu, which inform the selection of the OSIRIS-REx sample site. These, in turn, are essential for understanding the provenance of the regolith sample collected by the OSIRIS-REx spacecraft. The OLA data also are important for quantifying any hazards near the selected OSIRIS-REx sample site and for evaluating the range of tilts at the sampling site for comparison against the capabilities of the sample acquisition device.

  14. OSIRIS (the first step). A user guide

    International Nuclear Information System (INIS)

    Engberg, D.

    1999-01-01

    The OSIRIS Project will explore the instrumental horizons available with the cold neutrons from a pulsed source and especially the totally new avenues available to polarised neutrons on these sources. On pulsed sources, polarisation techniques offer great potential for high resolution studies, and only lack of opportunity has left the field unexploited. On OSIRIS, the fundamentally novel methods developed on IRIS will be combined with proven and extended neutron polarising techniques. The high flux available at ISIS, coupled to the advanced design of the OSIRIS guide, will provide the means to take this field to its next evolutionary stage. By exploiting the combination of sharp pulses, white beams and cold neutrons from ISIS, high resolution measurements, both dynamic and structural, can be carried out using both unpolarised and polarised neutrons. The OSIRIS Project is an international collaboration involving India, Italy, Spain, Sweden, Switzerland and the United Kingdom. The project has three well-defined phases; phase 1: Extraction of a second cold beam guide from the IRIS beam line; phase 2: large d-spacing powder diffraction, incident beam polarised powder diffraction; phase 3: high resolution spectroscopy, spectroscopy polarisation analysis, diffraction polarisation analysis. This is the user manual for the first step of the OSIRIS project, which means that phase 2 is now almost finished, i.e. we have a high resolution large d-spacing diffractometer, but the incident beam polarisation is as of yet only used for tests. You can find more information on the Osiris web-pages at . This document is also available in an html version at that address. This document is divided into five different parts. First, this short introduction, then what you need to think about before your arrive at ISIS, thereafter, the different parts of the instrument are described, together with some examples of sample environments. Fourthly, the actual running of an experiment is dealt

  15. Role of irradiation reactor mock-ups

    International Nuclear Information System (INIS)

    Casali, F.; Cerles, J.M.; Debrue, J.

    1977-01-01

    A survey is given of the utilization of low power facilities in support to irradiation reactor experiments. The BRO2, ISIS and RB3 facilities are described as neutronic mock-ups of the BR2, OSIRIS and ESSOR reactors respectively

  16. Sandia National Laboratories results for the 2010 criticality accident dosimetry exercise, at the CALIBAN reactor, CEA Valduc France.

    Energy Technology Data Exchange (ETDEWEB)

    Ward, Dann C.

    2011-09-01

    This document describes the personal nuclear accident dosimeter (PNAD) used by Sandia National Laboratories (SNL) and presents PNAD dosimetry results obtained during the Nuclear Accident Dosimeter Intercomparison Study held 20-23 September, 2010, at CEA Valduc, France. SNL PNADs were exposed in two separate irradiations from the CALIBAN reactor. Biases for reported neutron doses ranged from -15% to +0.4% with an average bias of -7.7%. PNADs were also exposed on the back side of phantoms to assess orientation effects.

  17. Sandia National Laboratories results for the 2010 criticality accident dosimetry exercise, at the CALIBAN reactor, CEA Valduc France

    International Nuclear Information System (INIS)

    Ward, Dann C.

    2011-01-01

    This document describes the personal nuclear accident dosimeter (PNAD) used by Sandia National Laboratories (SNL) and presents PNAD dosimetry results obtained during the Nuclear Accident Dosimeter Intercomparison Study held 20-23 September, 2010, at CEA Valduc, France. SNL PNADs were exposed in two separate irradiations from the CALIBAN reactor. Biases for reported neutron doses ranged from -15% to +0.4% with an average bias of -7.7%. PNADs were also exposed on the back side of phantoms to assess orientation effects.

  18. Development, calibration and experimental results obtained with an innovative calorimeter (CALMOS) for nuclear heating measurements

    International Nuclear Information System (INIS)

    Carcreff, H.; Cloute-Cazalaa, V.; Salmon, L.

    2011-01-01

    Nuclear heating inside an MTR reactor has to be known in order to be able to control samples temperature during irradiation experiments. An R and D program has been carried out at CEA to design a new type of in-core calorimetric system. This new development, started in 2002, has for main objective to manufacture a calorimeter suitable to monitoring nuclear heating inside the 70 MWth OSIRIS material testing reactor operated by CEA's Nuclear Energy Div. at the Saclay research center. An innovative calorimetric probe, associated to a specific handling system, has been designed to provide access to measurements both along the fissile height and on the upper part of the core, where nuclear heating still remains high. Two mock-ups of the probe were manufactured and tested in 2005 and 2009 in ex-core area of OSIRIS reactor for process validation, while a displacement system has been especially studied to move the probe along a given axial measurement range. This paper deals with the development, tests on preliminary mock-ups and the finalization of the probe. Main modeling and experimental results are presented. Moreover, alternative methods to calibration for nuclear heating rate measurements which are now possible with this new calorimeter are presented and discussed. (authors)

  19. Development, calibration, and experimental results obtained with an innovative calorimeter (CALMOS) for nuclear heating measurements

    International Nuclear Information System (INIS)

    Carcreff, Hubert; Cloute-Cazalaa, Veronique; Salmon, Laurent

    2012-01-01

    Nuclear heating inside an MTR reactor has to be known in order to be able to control samples temperature during irradiation experiments. An R and D program has been carried out at CEA to design a new type of in-core calorimetric system. This new development, started in 2002, has for main objective to manufacture a calorimeter suitable to monitoring nuclear heating inside the 70 MWth OSIRIS material testing reactor operated by CEA's Nuclear Energy Division at the Saclay research center. An innovative calorimetric probe, associated to a specific handling system, has been designed to provide access to measurements both along the fissile height and on the upper part of the core, where nuclear heating still remains high. Two mock-ups of the probe were manufactured and tested in 2005 and 2009 in ex-core area of OSIRIS reactor for process validation, while a displacement system has been especially studied to move the probe along a given axial measurement range. This paper deals with the development, tests on preliminary mock-ups and the finalization of the probe. Main modeling and experimental results are presented. Moreover, alternative methods to calibration for nuclear heating rate measurements which are now possible with this new calorimeter are presented and discussed. (authors)

  20. Research reactors and materials testing

    International Nuclear Information System (INIS)

    Vidal, H.

    1986-01-01

    Research reactors can be classified in three main groups according to the moderator which is used. Their technical characteristics are given and the three most recent research and materials testing reactors are described: OSIRIS, ORPHEE and the high-flux reactor of Grenoble. The utilization of research reactors is reviewed in four fields of activity: training, fundamental or applied research and production (eg. radioisotopes) [fr

  1. Fusion technology. Annual report of the. Association Cea/EURATOM; Technologie de fusion.Rapport annuel de l`association CEA/Euratom

    Energy Technology Data Exchange (ETDEWEB)

    Magaud, P; Le Vagueres, F

    1997-12-31

    In 1996, the French EURATOM-CEA Association made significant contributions to the European technology programme. This work is compiled in this report as follows: the ITER CEA activities and related developments are described in the first section; blankets and material developments for DEMO, long term safety studies are summarised in the second part; the Underlying Technology activities are compiled in the third part of this report. In each section, the tasks are sorted out to respect the European presentation. For an easy reading, appendix 4 gives the list of tasks in alphabetical order with a page reference list. The CEA is in charge of the French Technology programme. Three specific organizational directions of the CEA, located on four sites (see appendix 5) are involves in this programme: Advanced Technologies Direction (DTA), for Material task; Nuclear Reactors Direction (DRN), for Blanket design, Neutronic problems, Safety tasks; Physical Sciences Direction (DSM) uses the competence of the Tore Supra team in the Magnet design and plasma Facing Component field. The CEA programme is completed by collaborations with Technicatome, COMEX-Nucleaire and Ecole Polytechnique. The breakdown of the programme by Directions is presented in figure 1. The allocation of tasks is given in appendix 2 and in appendix 3, the related publications. (author).

  2. Fusion technology. Annual report of the. Association Cea/EURATOM; Technologie de fusion.Rapport annuel de l`association CEA/Euratom

    Energy Technology Data Exchange (ETDEWEB)

    Magaud, P.; Le Vagueres, F.

    1996-12-31

    In 1996, the French EURATOM-CEA Association made significant contributions to the European technology programme. This work is compiled in this report as follows: the ITER CEA activities and related developments are described in the first section; blankets and material developments for DEMO, long term safety studies are summarised in the second part; the Underlying Technology activities are compiled in the third part of this report. In each section, the tasks are sorted out to respect the European presentation. For an easy reading, appendix 4 gives the list of tasks in alphabetical order with a page reference list. The CEA is in charge of the French Technology programme. Three specific organizational directions of the CEA, located on four sites (see appendix 5) are involves in this programme: Advanced Technologies Direction (DTA), for Material task; Nuclear Reactors Direction (DRN), for Blanket design, Neutronic problems, Safety tasks; Physical Sciences Direction (DSM) uses the competence of the Tore Supra team in the Magnet design and plasma Facing Component field. The CEA programme is completed by collaborations with Technicatome, COMEX-Nucleaire and Ecole Polytechnique. The breakdown of the programme by Directions is presented in figure 1. The allocation of tasks is given in appendix 2 and in appendix 3, the related publications. (author).

  3. The OVIRS Visible/IR Spectrometer on the OSIRIS-Rex Mission

    Science.gov (United States)

    Reuter, D. C.; Simon-Miller, A. A.

    2012-01-01

    The OSIRIS-REx (Origins Spectral Interpretation Resource Identification Security Regolith Explorer) Mission is a planetary science mission to study, and return a sample from, the carbonaceous asteroid 1999 RQ-36. The third mission selected under NASA's New Frontiers Program, it is scheduled to be launched in 2016. It is led by PI Dante Lauretta at the University of Arizona and managed by NASA's Goddard Space Flight Center. The spacecraft and the asteroid sampling mechanism, TAGSAM (Touch-And-Go Sample Acquisition Mechanism) will be provided by Lockheed Martin Space Systems. Instrumentation for studying the asteroid include: OCAMS (the OSIRIS-REx Camera Suite), OLA (the OSIRIS-REx Laser Altimeter, a scanning LIDAR), OTES (The OSIRIS-REx Thermal Emission Spectrometer, a 4-50 micron point spectrometer) and OVIRS (the OSIRIS-REx Visible and IR Spectrometer, a 0.4 to 4.3 micron point spectrometer). The payload also includes REXIS (the Regolith X-ray Imaging Spectrometer) a student provided experiment. This paper presents a description of the OVIRS instrument.

  4. OSIRIS-REx Contamination Control Strategy and Implementation

    Science.gov (United States)

    Dworkin, J. P.; Adelman, L. A.; Ajluni, T.; Andronikov, A. V.; Aponte, J. C.; Bartels, A. E.; Beshore, E.; Bierhaus, E. B.; Brucato, J. R.; Bryan, B. H.; Burton, A. S.; Callahan, M. P.; Castro-Wallace, S. L.; Clark, B. C.; Clemett, S. J.; Connolly, H. C.; Cutlip, W. E.; Daly, S. M.; Elliott, V. E.; Elsila, J. E.; Enos, H. L.; Everett, D. F.; Franchi, I. A.; Glavin, D. P.; Graham, H. V.; Hendershot, J. E.; Harris, J. W.; Hill, S. L.; Hildebrand, A. R.; Jayne, G. O.; Jenkens, R. W.; Johnson, K. S.; Kirsch, J. S.; Lauretta, D. S.; Lewis, A. S.; Loiacono, J. J.; Lorentson, C. C.; Marshall, J. R.; Martin, M. G.; Matthias, L. L.; McLain, H. L.; Messenger, S. R.; Mink, R. G.; Moore, J. L.; Nakamura-Messenger, K.; Nuth, J. A.; Owens, C. V.; Parish, C. L.; Perkins, B. D.; Pryzby, M. S.; Reigle, C. A.; Righter, K.; Rizk, B.; Russell, J. F.; Sandford, S. A.; Schepis, J. P.; Songer, J.; Sovinski, M. F.; Stahl, S. E.; Thomas-Keprta, K.; Vellinga, J. M.; Walker, M. S.

    2018-02-01

    OSIRIS-REx will return pristine samples of carbonaceous asteroid Bennu. This article describes how pristine was defined based on expectations of Bennu and on a realistic understanding of what is achievable with a constrained schedule and budget, and how that definition flowed to requirements and implementation. To return a pristine sample, the OSIRIS-REx spacecraft sampling hardware was maintained at level 100 A/2 and scientists, engineers, managers, and technicians.

  5. Status of CEA reactor studies for a 200 kWe turboelectric Space Power System

    International Nuclear Information System (INIS)

    Carre, F.; Gervaise, F.; Proust, E.; Schwartz, J.P.; Tilliette, Z.; Vrillon, B.

    1986-01-01

    A reference design for a 200 kWe Space Nuclear Power System has been developed by the CNES and CEA Agencies of the French Government in order to assess within a first study phase running from mid 1984 to mid 1986, the key feasibility issues and the development cost of a Space Power System compatible with the version of the European launcher (ARIANE V), that will be available after 1995, and with adequate power range and lifetime performances for the missions considered at that time. The heat from a fast spectrum lithium cooled reactor is converted by a turboelectric system, selected for its technological readiness and for its advantage over thermionics and thermoelectricity, of minimizing the total mass of 100 to 300 kWe power systems, considering the available radiator area afforded by the specific ARIANE V geometrical features. A heat pipe radiator is preferred to an equivalent gas cooled system, for the increased reliability brought by the large number of independent cooling elements. The successive topics addressed in the paper, include a description of the system main components and steady state operating conditions, and the present views about the start up procedure and the reactor control

  6. Dismantling at the CEA's Nuclear Energy Division: strategy and programmes

    International Nuclear Information System (INIS)

    Lecomte, C.; Prunele, D. de; Rozain, J.P.; Nokhamzon, J.G.; Tallec, M.

    2008-01-01

    The CEA's Nuclear Energy Division (DEN) nuclear facilities currently include seventeen reactors and thirty six other miscellaneous facilities, particularly laboratories, fuel processing units and facilities specific to waste management. Some of these are currently being dismantled or must be dismantled soon so that the DEN, the Nuclear Energy Division, can construct new equipment and thus have available a range of R and D facilities in line with the issues of the nuclear industry of the future. At CEA, the first nuclear facility dismantling operations go back several dozen years and involve numerous and varied facilities. The first operations of any significance took place in the 1960's and 1970's and covered, for example, the first plutonium plant at Fontenay-aux-Roses (total dismantling) and small research reactors or critical models - CESAR and PEGGY at Cadarache and MINERVE at Fontenay-aux Roses (civil engineering cleaned up and kept). At La Hague, the dismantling of AT1, a pilot workshop used by the CEA during the 1970's to process irradiated fuels from fast neutron reactors, was completed in March 2001 (IAEA former stage 3, excluding civil engineering demolition). On the other hand, during this period of first dismantling, the intermediate-sized reactors (G1, Rapsodie) were only partially dismantled after shut down, mainly due to the lack of graphite and sodium waste management routes at the time. About twenty facilities were thus dealt with up to 2001, in other words about half of all the nuclear facilities shut down permanently before this date. (authors)

  7. Review of nuclear data improvement needs for nuclear radiation measurement techniques used at the CEA experimental reactor facilities

    Directory of Open Access Journals (Sweden)

    Destouches Christophe

    2016-01-01

    Full Text Available The constant improvement of the neutron and gamma calculation codes used in experimental nuclear reactors goes hand in hand with that of the associated nuclear data libraries. The validation of these calculation schemes always requires the confrontation with integral experiments performed in experimental reactors to be completed. Nuclear data of interest, straight as cross sections, or elaborated ones such as reactivity, are always derived from a reaction rate measurement which is the only measurable parameter in a nuclear sensor. So, in order to derive physical parameters from the electric signal of the sensor, one needs specific nuclear data libraries. This paper presents successively the main features of the measurement techniques used in the CEA experimental reactor facilities for the on-line and offline neutron/gamma flux characterizations: reactor dosimetry, neutron flux measurements with miniature fission chambers and Self Power Neutron Detector (SPND and gamma flux measurements with chamber ionization and TLD. For each technique, the nuclear data necessary for their interpretation will be presented, the main identified needs for improvement identified and an analysis of their impact on the quality of the measurement. Finally, a synthesis of the study will be done.

  8. Report transparency and nuclear safety 2007 CEA Cadarache

    International Nuclear Information System (INIS)

    2007-01-01

    This report presents the activities of the CEA Center of Cadarache for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially the report discusses the beginning of the RJH reactor construction, the fourth generation reactors research programs, the implementing of la Rotonde the new radioactive wastes management installation, the renovation of the LECA. (A.L.B.)

  9. OSIRIS-REx Contamination Control Strategy and Implementation

    Science.gov (United States)

    Dworkin, J. P.; Adelman, L. A.; Ajluni, T. M.; Andronikov, A. V.; Aponte, J. S.; Bartels, A. E.; Beshore, E.; Bierhaus, E. B.; Brucato, J. R.; Bryan, B. H.; hide

    2017-01-01

    OSIRIS-REx will return pristine samples of carbonaceous asteroid Bennu. This article describes how pristine was defined based on expectations of Bennu and on a realistic understanding of what is achievable with a constrained schedule and budget, and how that definition flowed to requirements and implementation. To return a pristine sample, the OSIRIS-REx spacecraft sampling hardware was maintained at level 100 A/2 and less than 180 ng/cm(exp 2) of amino acids and hydrazine on the sampler head through precision cleaning, control of materials, and vigilance. Contamination is further characterized via witness material exposed to the spacecraft assembly and testing environment as well as in space. This characterization provided knowledge of the expected background and will be used in conjunction with archived spacecraft components for comparison with the samples when they are delivered to Earth for analysis. Most of all, the cleanliness of the OSIRIS-REx spacecraft was achieved through communication among scientists, engineers, managers, and technicians.

  10. CEA - Nuclear Energy Division. Report on Sustainable Radioactive Waste Management

    International Nuclear Information System (INIS)

    2012-12-01

    The Sustainable Radioactive Waste Management Act of June 28, 2006, specified clear guidelines for spent nuclear fuel management. It states two complementary principles: - The policy of treating and recycling spent nuclear fuel is valid for reducing the quantity and toxicity of suitably packaged ultimate radioactive waste-forms. - The reference process for high-activity and long-lived ultimate waste is deep geological disposal. The report prepared by the CEA in response to these requirements was completed after several years of work in cooperation with the other French actors in this field (EDF, AREVA) and with contribution of the CNRS and Andra. It addresses the following topics in several volumes: n guidelines for research on 4. generation systems, and a description of the various systems examined; - the results of research coordinated by the CEA on partitioning and transmutation of long-lived radioactive elements; - choices proposed for the Astrid integrated technology demonstrator - a sodium-cooled fast reactor (SFR) - and a reasonable timetable for its construction; - a review of research conducted around the world on 4. generation systems based on fast neutron reactors (FNRs). The principal results and findings compiled by the CEA from these studies are summarized in this document

  11. Research and materials irradiation reactors

    International Nuclear Information System (INIS)

    Ballagny, A.; Guigon, B.

    2004-01-01

    Devoted to the fundamental and applied research on materials irradiation, research reactors are nuclear installations where high neutrons flux are maintained. After a general presentation of the research reactors in the world and more specifically in France, this document presents the heavy water cooled reactors and the water cooled reactors. The third part explains the technical characteristics, thermal power, neutron flux, operating and details the Osiris, the RHF (high flux reactor), the Orphee and the Jules Horowitz reactors. The last part deals with the possible utilizations. (A.L.B.)

  12. Report transparency and nuclear safety 2007 CEA Saclay; Rapport transparence et securite nucleaire 2007 CEA Saclay

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This report presents the activities of the CEA Center of Saclay for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially two public consultation on release authorizations and the Neurospin installations, the dismantling of the 49 nuclear installation, the shutdown of the learning reactor ULYSSE are detailed. (A.L.B.)

  13. Fusion technology. Annual report of the. Association Cea/EURATOM

    International Nuclear Information System (INIS)

    Magaud, P.; Le Vagueres, F.

    1996-01-01

    In 1996, the French EURATOM-CEA Association made significant contributions to the European technology programme. This work is compiled in this report as follows: the ITER CEA activities and related developments are described in the first section; blankets and material developments for DEMO, long term safety studies are summarised in the second part; the Underlying Technology activities are compiled in the third part of this report. In each section, the tasks are sorted out to respect the European presentation. For an easy reading, appendix 4 gives the list of tasks in alphabetical order with a page reference list. The CEA is in charge of the French Technology programme. Three specific organizational directions of the CEA, located on four sites (see appendix 5) are involves in this programme: Advanced Technologies Direction (DTA), for Material task; Nuclear Reactors Direction (DRN), for Blanket design, Neutronic problems, Safety tasks; Physical Sciences Direction (DSM) uses the competence of the Tore Supra team in the Magnet design and plasma Facing Component field. The CEA programme is completed by collaborations with Technicatome, COMEX-Nucleaire and Ecole Polytechnique. The breakdown of the programme by Directions is presented in figure 1. The allocation of tasks is given in appendix 2 and in appendix 3, the related publications. (author)

  14. OSIRIS reactor radioprotection, radioprotection measurements performed during the power rise and the first 50 megawatt operation; Radioprotection de la pile OSIRIS, mesures de radioprotection effectuees au cours de la montee en puissance et des premiers fonctionnements a 50 megawatts

    Energy Technology Data Exchange (ETDEWEB)

    Fanton, B; Lebouleux, P

    1967-12-01

    The authors supply the results of the measurements that have been made near the Osiris reactor during the power increase and during the first functioning at 50 megawatts. The measurements relate to the absorbed dose rates in the premises, the water activation and the atmospheric contamination. The influence of the heat layer of water movements and the water rate in the core chimney on the absorbed dose rate at the footbridge level overhanging the pile core has been studied. The modifications to the protection devices that have been proposed after the measurements and the effect of these modifications on the results of the measures are given then. The regeneration process of a water purification chain has been examined from the radiation protection point of view. It has been possible to make some twenty radionuclides obvious in the produced effluents and to determine the volume activity of these effluents for each radionuclide. The whole of results show that in a general way, the irradiation levels are low during the usual reactor functioning. [French] Les auteurs fournissent les resultats des mesures de radioprotection oui ont ete effectuees aupres de la pile Osiris pendant la montee en puissance et au cours des premiers fonctionnements a 50 megawatts. Les mesures portent sur les debits de dose absorbee dans les locaux, l'activation de l'eau et la contamination atmospherique. L'influence de la couche chaude des mouvements d'eau et du debit d'eau dans la cheminee du coeur sur le debit de dose absorbee au niveau de la passerelle surplombant le coeur de la pile, a ete etudiee. Les modifications aux dispositifs de protection, qui ont ete proposees a la suite des mesures, et l'effet de ces modifications sur les resultats des mesures sont indiques ensuite. Le processus de regeneration d'une chaine d'epuration de l'eau a ete examine sous l'angle de la radioprotection. Il a ete possible de mettre en evidence une vingtaine de radionucleides dans les effluents produits et de

  15. Development and experimental qualification of a calculation scheme for the evaluation of gamma heating in experimental reactors. Application to MARIA and Jules Horowitz (JHR) MTR Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Tarchalski, M.; Pytel, K.; Wroblewska, M.; Marcinkowska, Z.; Boettcher, A.; Prokopowicz, R. [NCBJ Institute, MARIA Reactor, ul.Andrzeja Soltana 7, 05-400 Swierk (Poland); Sireta, P.; Gonnier, C.; Bignan, G. [CEA, DEN, Reactor Studies Department, Cadarache, F-13108 St-Paul-Lez-Durance (France); Lyoussi, A.; Fourmentel, D.; Barbot, L.; Villard, J.F.; Destouches, C. [CEA, DEN, DER, Instrumentation Sensors and Dosimetry Laboratory, Cadarache, F-13108 St-Paul-Lez-Durance (France); Reynard-Carette, C.; Brun, J. [Aix Marseille Universite, CNRS, Universite de Toulon, IM2NP UMR 7334, 13397, Marseille (France); Jagielski, J. [NCBJ Institute, MARIA Reactor, ul.Andrzeja Soltana 7, 05-400 Swierk (Poland); Institute of Electronic Materials Technolgy, Wolczynska 133, 01-919 Warszawa (Poland); Luks, A. [Institute of Heat Engineering, Nowowiejska 21/25, 00-665 Warsaw (Poland)

    2015-07-01

    Precise computational determination of nuclear heating which consists predominantly of gamma heating (more than 80 %) is one of the challenges in material testing reactor exploitation. Due to sophisticated construction and conditions of experimental programs planned in JHR it became essential to use most accurate and precise gamma heating model. Before the JHR starts to operate, gamma heating evaluation methods need to be developed and qualified in other experimental reactor facilities. This is done inter alia using OSIRIS, MINERVE or EOLE research reactors in France. Furthermore, MARIA - Polish material testing reactor - has been chosen to contribute to the qualification of gamma heating calculation schemes/tools. This reactor has some characteristics close to those of JHR (beryllium usage, fuel element geometry). To evaluate gamma heating in JHR and MARIA reactors, both simulation tools and experimental program have been developed and performed. For gamma heating simulation, new calculation scheme and gamma heating model of MARIA have been carried out using TRIPOLI4 and APOLLO2 codes. Calculation outcome has been verified by comparison to experimental measurements in MARIA reactor. To have more precise calculation results, model of MARIA in TRIPOLI4 has been made using the whole geometry of the core. This has been done for the first time in the history of MARIA reactor and was complex due to cut cone shape of all its elements. Material composition of burnt fuel elements has been implemented from APOLLO2 calculations. An experiment for nuclear heating measurements and calculation verification has been done in September 2014. This involved neutron, photon and nuclear heating measurements at selected locations in MARIA reactor using in particular Rh SPND, Ag SPND, Ionization Chamber (all three from CEA), KAROLINA calorimeter (NCBJ) and Gamma Thermometer (CEA/SCK CEN). Measurements were done in forty points using four channels. Maximal nuclear heating evaluated from

  16. Scientific evaluation at the French Atomic Energy Commission (CEA). 2005-2006 annual report; L'evaluation scientifique au CEA. Rapport annuel 2005-2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This report aims at presenting the scientific evaluation activities carried out at the CEA during the years 2005-2006. The evaluation system is described in detail. It comprises two aspects: the evaluation of the scientific policy implemented by the scientific Council and by the visiting committee of the CEA, and the evaluation of the laboratories, performed by a pool of 36 scientific councils. The evaluation by external and independent parties is the key point of this system. This document makes a status of the evaluations performed in 2005 and 2006. It presents a synthesis of the conclusions of the evaluation authorities. The actions implemented by the CEA to take into consideration the recommendations are also reported with the improvements noticed. The two topics examined by the scientific Committee and by the visiting committee were dealing with the energy domain, which is a strategic issue for the CEA. The examination of the researches on future nuclear reactors and on new energy technologies have shown the major role played by the CEA in the recent advances in these domains. About 95% of the laboratories activity was examined during the 2002-2005 period. The richness of the remarks and recommendations made by the scientific councils should allow the CEA to improve the quality and relevance of its research works. The start-up of the 2006-2009 evaluation cycle has been the occasion to modify the evaluation of some research domains in order to take into account the evolution of programs. The evaluation system of the CEA is highly consistent with the AERES principles. Its implementation, adapted to each type of activity (fundamental research, applied research, technological developments) allows the CEA to follow up a permanent improvement approach. (J.S.)

  17. APR1400 CEA Withdrawal at Power Accident Analysis using KNAP

    International Nuclear Information System (INIS)

    Lee, Dong-Hyuk; Yang, Chang-Keun; Kim, Yo-Han; Sung, Chang-Kyung

    2006-01-01

    KEPRI (Korea Electric Power Research Institute) has been developing safety analysis methodology for non- LOCA (Loss Of Coolant Accident) analysis of OPR1000 (Optimized Power Reactor 1000, formerly KSNP). The new methodology, named KNAP (Korea Non-LOCA Analysis Package), uses RETRAN as the main system analysis code. RETRAN code is a non- LOCA safety analysis code developed by EPRI. The new methodology will replace existing CE (Combustion Engineering) supplied codes and methodologies currently used in non-LOCA analysis of OPR1000. In this paper, we apply KNAP methodology to APR1400 (Advanced Power Reactor 1400). The CEA (Control Element Assembly) withdrawal at power accident is one of the 'reactivity and power distribution anomalies' events and the results are typically described in the chapter 15.4.2 of SAR (Safety Analysis Report). The APR1400 has been designed to generate 1,400MWe of electricity with advanced features for greatly enhanced safety and economic goals. The CEA withdrawal at power analysis in APR1400 SSAR (Standard Safety Analysis Report) is analyzed with CESEC-III computer code. In this study, to confirm the applicability of the KNAP methodology and code system to APR1400, CEA withdrawal at power accident is analyzed using RETRAN code and it is compared with results from APR1400 SSAR

  18. The research reactors their contribution to the reactors physics; Les reacteurs de recherche leur apport sur la physique des reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Barral, J C [Electricite de France (EDF), 75 - Paris (France); Zaetta, A [CEA/Cadarache, Direction des Reacteurs Nucleaires, DRN, 13 - Saint-Paul-lez-Durance (France); Johner, J [CEA/Cadarache, Dept. de Recherches sur la Fusion Controlee (DRFC), 13 - Saint Paul lez Durance (France); Mathoniere, G [CEA/Saclay, DEN, 91 - Gif sur Yvette (France); and others

    2000-07-01

    The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

  19. Main technical options of the Jules Horowitz reactor project to achieve high flux performances and high safety level

    International Nuclear Information System (INIS)

    Ballagny, A.; Bergamaschi, Y.; Bouilloux, Y.; Bravo, X.; Guigon, B.; Rommens, M.; Tremodeux, P.

    2003-01-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it and will offer a quite larger experimental field. It has the ambition to provide the necessary nuclear data and to maintain a fission research capability in Europe after 2010. The Jules Horowitz Reactor will represent a significant step in terms of performances and experimental capabilities. This paper will present the main design option resulting from the preliminary studies. The choice of the specific power around 600 kW/I for the reference core configuration is a key decision to ensure the required flux level. Consequently many choices have to be made regarding the materials used in the core and the fuel element design. These involve many specific qualifications including codes validation. The main safety options are based on: - A safety approach based upon the defence-in-depth principle. - A strategy of generic approaches to assess experimental risks in the facility. - Internal events analysis taking into account risks linked to reactor and experiments (e.g., radioactive source-term). - Systematic consideration of external hazards (e.g., earthquake, airplane crash) and internal hazards. - Design of containment to manage and mitigate a severe reactor accident (consideration of 'BORAX' accident, according to french safety practice for MTRs, beyond design basis reactivity insertion accident, involving core melting and core destruction phenomena). (authors)

  20. Main technical options of the Jules Horowitz Reactor project to achieve high flux performances and high safety level

    International Nuclear Information System (INIS)

    Ballagny, A.; Bergamaschi, Y.; Bouilloux, Y.; Bravo, X.; Guigon, B.; Rommens, M.; Tremodeux, P.

    2003-01-01

    Since the shutdown of the SILOE reactor in 1997, the OSIRIS reactor has ensured the needs regarding technological irradiation at CEA including those of its industrial partners and customers. The Jules Horowitz Reactor will replace it and will offer a quite larger experimental field. It has the ambition to provide the necessary nuclear data and to maintain a fission research capability in Europe after 2010. The Jules Horowitz Reactor will represent a significant step in terms of performances and experimental capabilities. This paper will present the main design option resulting from the preliminary studies. The choice of the specific power around 600 KW/l for the reference core configuration is a key decision to ensure the required flux level. Consequently many choices have to be made regarding the materials used in the core and the fuel element design. These involve many specific qualifications including codes validation. The main safety options are based on: 1) A safety approach based upon the defence-in-depth principle. 2) A strategy of generic approaches to assess experimental risks in the facility. 3) Internal events analysis taking into account risks linked to reactor and experiments (eg., radioactive source-term). 4) Systematic consideration of external hazards (eg., earthquake, airplane crash) and internal hazards. 5) Design of containment to manage and mitigate a severe reactor accident (consideration of 'BORAX' accident, according to french safety practice for MTRs, beyond design basis reactivity insertion accident, involving core melting and core destruction phenomena). (author)

  1. Overview of CEA research in the field of radionuclides migration; Syntheses des recherches menees par le CEA sur la migration des radionucleides

    Energy Technology Data Exchange (ETDEWEB)

    Poinssot, Ch; Trotignon, L; Tevissen, E

    2006-07-01

    This report presents a synthetic status of the researches conducted within the Nuclear Energy Division (CEA/DEN) in the field of radionuclides migration in three specific areas which have been chosen for their representativeness and potential impact: the migration of RN in PWR reactors, the migration of RN from a deep geological repository and the migration processes in the surface environments. In addition, some status is given about more generic research which is conducted in the field of RN speciation in the aqueous phase and at the interfaces and regarding chemistry / transport couplings. Additional information about the human and technical means involved in these fields of research in CEA/DEN is finally given in the Appendix. (authors)

  2. Irradiation of four pencils fuel element clusters in the periphery of OSIRIS. Qualification of the calculation method by dosimetry

    International Nuclear Information System (INIS)

    Alberman, A.; Morin, C.

    1983-09-01

    The programs of qualification of PWR fuels required many irradiations in research reactors. In the periphery of the OSIRIS reactor (70 MW), two devices (IRENE and ISABELLE loops) recreating the environment of the fuel rods in power reactors have been put into service. In each device a fuel element cluster including four pencils was irradiated. The problem set by dosimetry was to calculate the enrichments of the pencils to obtain the required power level and to compensate the neutron flux gradient (in front of/behind) to obtain the same power on each one of the four pencils. The required accuracy is about 5%. Fuels dosimetry achieved on loops mockups in the ISIS reactor allowed to test the validity of the calculations and to calibrate the probes according to the nuclear power [fr

  3. Report of the CEA visiting committee on R and D for future nuclear energy systems, May 11-13, 2005

    International Nuclear Information System (INIS)

    Brechet, Y.; Ebbesen, T.; Fujiie, Y.; Richter, B.; Stormer, H.; Zinkle, S.J.

    2005-01-01

    This was the fifth meeting of the Visiting Committee of the CEA since its creation in year 2000. The first meeting gave members of the committee a broad overview of the entire spectrum of CEA research and subsequent meetings have focused on specific topics. These included the nuclear fuel cycle, biology, and micro and nano technologies. This meeting focused on research and development for future nuclear energy systems. The main division of CEA concerned with this topic is the Nuclear Energy Division. Some of the laboratories of the Technological Research and Matter Science Divisions are also involved in areas such as materials and basic nuclear data. The report deals with the fuels and waste, the SFR (Sodium Fast Reactor) and GFR (Gas Fast Reactor) programs, the Very High temperature reactor (VHTR), the actinide separation, the materials, the irradiation tests facilities and the personnel for the future. (A.L.B.)

  4. Report of the CEA visiting committee on R and D for future nuclear energy systems, May 11-13, 2005

    Energy Technology Data Exchange (ETDEWEB)

    Brechet, Y. [Institut National Polytechnique, ENSEEG/LTPCM, 38 - Grenoble (France); Ebbesen, T. [Universite Louis Pasteur, ISIS, 67 - Strasbourg (France); Fujiie, Y. [Nuclear Salon Fuj-ie (Japan); Richter, B. [Director Emeritus, Stanford Linear Accelerator Center (United States); Stormer, H. [Columbia Univ., Dept. of Physics (United States); Zinkle, S.J. [Oac Ridge National Laboratory, Metals and Ceramics Div. (United States)

    2005-07-01

    This was the fifth meeting of the Visiting Committee of the CEA since its creation in year 2000. The first meeting gave members of the committee a broad overview of the entire spectrum of CEA research and subsequent meetings have focused on specific topics. These included the nuclear fuel cycle, biology, and micro and nano technologies. This meeting focused on research and development for future nuclear energy systems. The main division of CEA concerned with this topic is the Nuclear Energy Division. Some of the laboratories of the Technological Research and Matter Science Divisions are also involved in areas such as materials and basic nuclear data. The report deals with the fuels and waste, the SFR (Sodium Fast Reactor) and GFR (Gas Fast Reactor) programs, the Very High temperature reactor (VHTR), the actinide separation, the materials, the irradiation tests facilities and the personnel for the future. (A.L.B.)

  5. CEA Annual report 2007; CEA rapport annuel 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The CEA, a prominent player in research development and innovation, is active in three main domains: energy, health care and information technology, defense and security. This annual report presents the CEA activities for the year 2007 in these three main areas: science and technology working for nuclear deterrence and global security, the energies without greenhouse effect gases emission against the climatic change, researches in the information sciences and technologies for a better communication and health. The CEA safety, organization, communication and international relations are also presented. (A.L.B.)

  6. Importance of low-level radioactive wastes in dismantling strategy in CEA (FRANCE)

    International Nuclear Information System (INIS)

    Lafaille, C.

    1991-01-01

    This paper describes the advance used in C.E.A. to realize dismantling operations in the best technical and economical conditions. Particularly, for low-level radioactive waste management CEA's advance defines, first, the final destination of dismantling materials: - recycling in public lands for level activity inferior to 1 Bq/g; directly or after transformation (melting, calcination, extrusion) - storage in a ground disposal, after compacting, encapsulation or drumming. Two examples are given: - Marcoule G2 - G3 reactor dismantling - Gaseous diffusion plants demolition (COGEMA Pierrelatte)

  7. OSIRIS and SOMBRERO Inertial Fusion Power Plant Designs, Volume 2: Designs, Assessments, and Comparisons

    Energy Technology Data Exchange (ETDEWEB)

    Meier, W. R.; Bieri, R. L.; Monsler, M. J.; Hendricks, C. D.; Laybourne, P.; Shillito, K. R.

    1992-03-01

    This is a comprehensive design study of two Inertial Fusion Energy (IFE) electric power plants. Conceptual designs are presented for a fusion reactor (called Osiris) using an induction-linac heavy-ion beam driver, and another (called SOMBRERO) using a KrF laser driver. The designs covered all aspects of IFE power plants, including the chambers, heat transport and power conversion systems, balance-of-plant facilities, target fabrication, target injection and tracking, as well as the heavy-ion and KrF drivers. The point designs were assessed and compared in terms of their environmental & safety aspects, reliability and availability, economics, and technology development needs.

  8. Some general remarks concerning the experimental devices and means for flux measurements used in the research reactors of the C.E.A

    International Nuclear Information System (INIS)

    Rossillon, F.; Chauvez, C.

    1964-01-01

    First, the authors define the operation and organisation lay-out of the research reactors. This out lay is then used as a basis for an examination of the conception, realisation and exploitation of irradiation devices. They then analyse the different operations carried out in placing an irradiation device in the reactor. They point out that the time necessary for decision of construction, conception, for material provision, for construction, out-of-pile tests and security examination is in general longer than the irradiation time. To minimize this time they advise a closer collaboration between the personnel of the experimentation laboratory and the reactor personnel for the conception of the design. They think it would be preferable to construct the prototypes in the research centre and leave the fabrication of small series to the industry. The methods used for the in-pile operation of the device are also indicated. Considering the evolution of the construction techniques they mention that the requirements for the irradiation conditions are put higher and higher (reactor stability and homogeneity). Also described are the performances of the main irradiation devices in operation in research reactor in the C.E.A. (authors) [fr

  9. Automating OSIRIS Data Reduction for the Keck Observatory Archive

    Science.gov (United States)

    Holt, J.; Tran, H. D.; Goodrich, R.; Berriman, G. B.; Gelino, C. R.; KOA Team

    2014-05-01

    By the end of 2013, the Keck Observatory Archive (KOA) will serve data from all active instruments on the Keck Telescopes. OSIRIS (OH-Suppressing Infra-Red Imaging Spectrograph), the last active instrument to be archived in KOA, has been in use behind the (AO) system at Keck since February 2005. It uses an array of tiny lenslets to simultaneously produce spectra at up to 4096 locations. Due to the complicated nature of the OSIRIS raw data, the OSIRIS team developed a comprehensive data reduction program. This data reduction system has an online mode for quick real-time reductions, which are used primarily for basic data visualization and quality assessment done at the telescope while observing. The offline version of the data reduction system includes an expanded reduction method list, does more iterations for a better construction of the data cubes, and is used to produce publication-quality products. It can also use reconstruction matrices that are developed after the observations were taken, and are more refined. The KOA team is currently utilizing the standard offline reduction mode to produce quick-look browse products for the raw data. Users of the offline data reduction system generally use a graphical user interface to manually setup the reduction parameters. However, in order to reduce and serve the 200,000 science files on disk, all of the reduction parameters and steps need to be fully automated. This pipeline will also be used to automatically produce quick-look browse products for future OSIRIS data after each night's observations. Here we discuss the complexities of OSIRIS data, the reduction system in place, methods for automating the system, performance using virtualization, and progress made to date in generating the KOA products.

  10. OSIRIS reactor radioprotection, radioprotection measurements performed during the power rise and the first 50 megawatt operation; Radioprotection de la pile OSIRIS, mesures de radioprotection effectuees au cours de la montee en puissance et des premiers fonctionnements a 50 megawatts

    Energy Technology Data Exchange (ETDEWEB)

    Fanton, B.; Lebouleux, P

    1967-12-01

    The authors supply the results of the measurements that have been made near the Osiris reactor during the power increase and during the first functioning at 50 megawatts. The measurements relate to the absorbed dose rates in the premises, the water activation and the atmospheric contamination. The influence of the heat layer of water movements and the water rate in the core chimney on the absorbed dose rate at the footbridge level overhanging the pile core has been studied. The modifications to the protection devices that have been proposed after the measurements and the effect of these modifications on the results of the measures are given then. The regeneration process of a water purification chain has been examined from the radiation protection point of view. It has been possible to make some twenty radionuclides obvious in the produced effluents and to determine the volume activity of these effluents for each radionuclide. The whole of results show that in a general way, the irradiation levels are low during the usual reactor functioning. [French] Les auteurs fournissent les resultats des mesures de radioprotection oui ont ete effectuees aupres de la pile Osiris pendant la montee en puissance et au cours des premiers fonctionnements a 50 megawatts. Les mesures portent sur les debits de dose absorbee dans les locaux, l'activation de l'eau et la contamination atmospherique. L'influence de la couche chaude des mouvements d'eau et du debit d'eau dans la cheminee du coeur sur le debit de dose absorbee au niveau de la passerelle surplombant le coeur de la pile, a ete etudiee. Les modifications aux dispositifs de protection, qui ont ete proposees a la suite des mesures, et l'effet de ces modifications sur les resultats des mesures sont indiques ensuite. Le processus de regeneration d'une chaine d'epuration de l'eau a ete examine sous l'angle de la radioprotection. Il a ete possible de mettre en evidence une vingtaine

  11. List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC. Reported period: January 1 to June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesministerium fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (ISTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. (orig./HP) [de

  12. List of reports in the field of reactor safety research from BMFT, CEA, EPRI, JSTA and USNRC. Reported period: July 1 to December 31, 1993

    International Nuclear Information System (INIS)

    1993-01-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of Reactor Safety Research. According to the cooperation of the Bundesministerium fuer Forschung und Technologie (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technologie Agency (ISTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Program of the BMFT, reporting organization. (orig./HP) [de

  13. 2012 review of French research reactors

    International Nuclear Information System (INIS)

    Estrade, Jerome

    2013-01-01

    Proposed by the French Reactor Operators' Club (CER), the meeting and discussion forum for operators of French research reactors, this report first gives a brief presentation of these reactors and of their scope of application, and a summary of highlights in 2012 for each of them. Then, it proposes more detailed presentations and reviews of characteristics, activities, highlights, objectives and results for the different types of reactors: neutron beam reactors (Orphee, High flux reactor-Laue-Langevin Institute or HFR-ILL), technological irradiation reactors (Osiris and Phenix), training reactors (Isis and Azur), reactors for safety research purposes (Cabri and Phebus), reactors for neutronic studies (Caliban, Prospero, Eole, Minerve and Masurca), and new research reactors (the RES facility and the Jules Horowitz reactor or JHR)

  14. Overview of CEA research in the field of radionuclides migration

    International Nuclear Information System (INIS)

    Poinssot, Ch.; Trotignon, L.; Tevissen, E.

    2006-01-01

    This report presents a synthetic status of the researches conducted within the Nuclear Energy Division (CEA/DEN) in the field of radionuclides migration in three specific areas which have been chosen for their representativeness and potential impact: the migration of RN in PWR reactors, the migration of RN from a deep geological repository and the migration processes in the surface environments. In addition, some status is given about more generic research which is conducted in the field of RN speciation in the aqueous phase and at the interfaces and regarding chemistry / transport couplings. Additional information about the human and technical means involved in these fields of research in CEA/DEN is finally given in the Appendix. (authors)

  15. How Packaging Fleet Renewal Fits French CEA Programs

    International Nuclear Information System (INIS)

    Dumesnil, J.; Malvache, P.; Hugon, F.C.; Sollacaro, M.

    2006-01-01

    CEA's (French Atomic Energy Agency) packaging fleet is dedicated to transportation of test irradiated fuels, of research reactors fuels, of navy propulsion fuels, and of waste coming from and to nuclear plants or facilities. This fleet encompasses more than 30 types of casks ranging from 5 to 30 tons, with either recent designs or other dating back to the seventies. A study has been launched in order to perform a global analysis of the life expectancy of the existing CEA and COGEMA Logistics cask fleets with respect to a 2015 target, in order to anticipate its renewal, while limiting the number of type of cask. Key elements like periodical evolutions of design and transport regulations, lessons learnt of existing casks (design, approval and extensions, operational feedback, maintenance and dismantling) are taken into account in order to ensure compliance and availability of the fleet. Moreover, from design to cask delivery, including regulatory tests, safety analysis report/ CoC, and manufacturing, 3 to 5 years is needed. Therefore cask development should be taken into account earlier of invest and research's programs. The paper will address the current life expectancy study of CEA and COGEMA Logistics packaging fleet, based on lessons learnt and regulation evolution and on general R and D plans by user facilities. It will show how a comprehensive optimized fleet is made available to CEA and other customers. Such a fleet combines optimized investment and uses, thus entailing synergies for well-mastered costs of transports. (authors)

  16. Refabricated and instrumented fuel rods

    International Nuclear Information System (INIS)

    Silberstein, K.

    2005-01-01

    Nuclear Fuel for power reactors capabilities evaluation is strongly based on the intimate knowledge of its behaviour under irradiation. This knowledge can be acquired from refabricated and instrumented fuel rods irradiated at different levels in commercial reactors. This paper presents the development and qualification of a new technique called RECTO related to a double-instrumented rod re-fabrication process developed by CEA/LECA hot laboratory facility at CADARACHE. The technique development includes manufacturing of the properly dimensioned cavity in the fuel pellet stack to house the thermocouple and the use of a newly designed pressure transducer. An analytic irradiation of such a double-instrumented fuel rod will be performed in OSIRIS test reactor starting October 2004. (Author)

  17. The Grenoble CEA Center: dismantled and rehabilitated

    International Nuclear Information System (INIS)

    Anon.

    2013-01-01

    The denuclearization program of the CEA center in Grenoble was launched in 2001. It involves 6 nuclear facilities (3 research reactors: Melusine, Siloette, and Siloe, and 1 laboratory (LAMA) and 2 units for processing wastes). The dismantling works were finished at the end of 2012 and the 2013 program concerns: the demolition of the buildings homing Melusine and Siloe reactors, the final rehabilitation of the Siloe raft, and the final rehabilitation of the laboratory and of the waste processing units. The budget is 117*10 6 euros for Siloe, 28*10 6 euros for Melusine, 6*10 6 euros for Siloette, 70*10 6 euros for the LAMA, and 90*10 6 euros for the 2 waste processing units. (A.C.)

  18. Report transparency and nuclear safety 2007 CEA Saclay

    International Nuclear Information System (INIS)

    2007-01-01

    This report presents the activities of the CEA Center of Saclay for the year 2007. The actions concerning the safety, the radiation protection, the significant events, the release control and the environmental impacts and the wastes stored on the center are discussed. More especially two public consultation on release authorizations and the Neurospin installations, the dismantling of the 49 nuclear installation, the shutdown of the learning reactor ULYSSE are detailed. (A.L.B.)

  19. List of reports in the field of reactor safety research sponsored by BMFT, CEA, EPRI, JSTA and USNRC. Reported period: April 1 - June 30, 1987

    International Nuclear Information System (INIS)

    1987-08-01

    The list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning single problems in the field of reactor safety research. According to the cooperation of the Federal Minister for Research and Technology (BMFT) with the Commissariat a l'Energie Atomique (CEA), the Japan Science and Technology Agency (JSTA), the Electric Power Research Institute (EPRI) and the United States Nuclear Regulatory Commission, these reports are available in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programme of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  20. CEA nuclear energy Directorate - Activity report 2012

    International Nuclear Information System (INIS)

    2013-01-01

    After an overview of the activities of the Directorate at the international level, of its scientific activities, and of the consideration given to quality, and a presentation of the transverse program on advanced materials, this report proposes presentations of activities in different domains: future nuclear industrial systems (reactors of 4. generation, back-end of the future cycle, sustainable management of nuclear materials, fundamental scientific and technological research), optimization of the present industrial nuclear activity (reactors of 2. and 3. generation, front-end and back-end of the fuel cycle), the main tools for nuclear development (numerical simulation, the Jules Horowitz reactor), valorisation, economic support of Haute-Marne and Meuse territories (the Syndiese project), nuclear dismantling and decontamination (dismantling projects, projects and works in Fontenay-aux-Roses, Grenoble and Saclay, waste and material flow management, nuclear service facilities, transports). It also presents the activities of some specific CEA centres like Marcoule (R and D in fuel cycle), Cadarache (future energies) and Saclay (nuclear sciences and simulation of reactors and fuel cycle)

  1. CEA sustainable development report 2007; CEA rapport developpement durable 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The CEA, a prominent player in research development and innovation, is active in three main domains: energy, health care and information technology, defense and security. This annual report presents the CEA activities in the domain of the sustainable development. The first part is devoted to the environment preservation policy (energy, water, air, chemistry, wastes, transport, buildings). The second part shows the dynamic governance in the domain of the risks management. The last part presents the CEA activities of research for the sustainable development. (A.L.B.)

  2. Examples of CEA managements of spent fuels from a prototype power reactor (PHENIX) and from commercial power reactors after post irradiation examinations

    International Nuclear Information System (INIS)

    Guay, P.

    1988-01-01

    CEA gained a good experience in the management of spent fuels from its research or power prototype reactors and of the fuel samples for post irradiation examinations. The solution for these products is the reprocessing. The delay to apply that solution is bound to the disponibility of the reprocessing facilities, and in several cases induce a delayed reprocessing. Only particular and limited fuels are planned to be sent in a definitive storage. The definitive storage is choosen only for a few fuels essentially requiring important modifications of the dissolution process. The treatments and operations on the spent fuels must be carried out following the French safety rules. Long and detailed flowsheet studies are therefore necessary before the setting up of the operations. Generally the cost of the management of limited quantities of fuels, as it is the case here, is high. The flowsheets are established in taking into account, as far as possible, the use of existing facilities, procedures, transport casks

  3. Drift-corrected Odin-OSIRIS ozone product: algorithm and updated stratospheric ozone trends

    Directory of Open Access Journals (Sweden)

    A. E. Bourassa

    2018-01-01

    Full Text Available A small long-term drift in the Optical Spectrograph and Infrared Imager System (OSIRIS stratospheric ozone product, manifested mostly since 2012, is quantified and attributed to a changing bias in the limb pointing knowledge of the instrument. A correction to this pointing drift using a predictable shape in the measured limb radiance profile is implemented and applied within the OSIRIS retrieval algorithm. This new data product, version 5.10, displays substantially better both long- and short-term agreement with Microwave Limb Sounder (MLS ozone throughout the stratosphere due to the pointing correction. Previously reported stratospheric ozone trends over the time period 1984–2013, which were derived by merging the altitude–number density ozone profile measurements from the Stratospheric Aerosol and Gas Experiment (SAGE II satellite instrument (1984–2005 and from OSIRIS (2002–2013, are recalculated using the new OSIRIS version 5.10 product and extended to 2017. These results still show statistically significant positive trends throughout the upper stratosphere since 1997, but at weaker levels that are more closely in line with estimates from other data records.

  4. Selection and use of a low enriched fuel in high performance research reactors

    International Nuclear Information System (INIS)

    Cerles, J.M.; Schwartz, J.P.

    1978-08-01

    A new nuclear fuel composition for research reactors (Osiris, Siloe) is studied using low enriched (E<20%) uranium oxide. Its utilization leads to modifications in the facilities of these experimental reactors: increase of primary coolant flow, modifications in failed element detection system, handling of materials and storage

  5. Some activities at CEA related to behaviour of core internals

    International Nuclear Information System (INIS)

    Petrequin, P.

    1998-01-01

    Eighteen transparencies where presented, elaborating some activities at CEA related to behaviour of core internals. After some introduction, ten of the transparencies are essentially a copy of the table of contents of the AMES report no. 11 (report no: EUR 17694 EN). The remaining 6 foils concerned themselves with irradiation experiments in test reactors, namely the IDAHO, CASIMIR and ALEXANDRA experiments

  6. Decommissioning works are going on at Fontenay-aux-roses CEA center

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    The CEA center of Fontenay-aux-roses is pursuing the dismantling operations of its nuclear installations. In 2003 120 glove boxes of the plutonium chemistry laboratory were disassembled and moved to the Cadarache CEA center. Hot cells from the Castor, Cyrano and Petrus lines are currently undergoing decontamination operations before being dismantled. As for the processing station of liquid effluents, the cutting works of the incinerator of low-level radioactive wastes and of the tanks began in 2003 and are expected to be over by end 2004. The Triton research reactor was decommissioned in 1982 and dismantling works on its hot cell and on its pool began at the end of 2003. (A.C.)

  7. A three-dimensional pin-wise analysis for CEA ejection accident

    Energy Technology Data Exchange (ETDEWEB)

    Park, Guen-Tae; Park, Min-Ho; Park, Jin-Woo; Um, Kil-Sup; Choi, Tong-Soo [KEPCO NF, Daejeon (Korea, Republic of)

    2016-10-15

    The ejection of a control element assembly (CEA) with high reactivity worth causes the sudden insertion of reactivity into the core. Immediately after the CEA ejection, the nuclear power of the reactor dramatically increases in an exponential behavior until the doppler effect becomes important and turns the reactivity balance and power down to lower levels. The 3-D CEA ejection analysis methodology has been developed using the multi-dimensional code coupling system, CHASER, which couples three dimensional core neutron kinetics code ASTRA, subchannel analysis code THALES, and fuel performance analysis code FROST using message passing interface (MPI). This paper presents the pin-by-pin level analysis result with the 3-D CEA ejection analysis methodology using the CHASER. The pin-by-pin level analysis consists of DNBR, enthalpy and Pellet/Clad Mechanical Interaction (PCMI) analysis. All the evaluations are simulated for APR1400 plant loaded with PLUS7 fuel. In this paper, the pin-by-pin analysis using the multidimensional core transient code, CHASER, is presented with respect to enthalpy, DNBR and PCMI for APR1400 plant loaded with PLUS7 fuel. For the pin-by-pin enthalpy and DNBR analysis, the quarter core for HFP case or 15 - 20 assemblies around the most severe assembly for part powers or HZP cases are selected. And PCMI calculation is performed for all the rods in the whole core during a conservative time period. The pin-by-pin analysis results show that the regulatory guidelines of CEA ejection accident are satisfied.

  8. Status of French reactors

    International Nuclear Information System (INIS)

    Ballagny, A.

    1997-01-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm 3 . The OSIRIS reactor has already been converted to LEU. It will use U 3 Si 2 as soon as its present stock of UO 2 fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU

  9. Immunological comparison of ovarian and colonic CEA

    International Nuclear Information System (INIS)

    Burtin, P.; Gendron, M.C.; Maunoury, M.T.; Lamerz, R.; Schnabel, G.

    1982-01-01

    Ovarian and colonic CEA were compared immunologically by means of antisera prepared against each of them. CEAs of both origins were found identical by immunodiffusion methods. In radioimmunological experiments, slight differences were observed between some but not all ovarian CEAs and colonic CEAs and also between different preparations of colonic CEA: no organ specificity of ovarian CEA could be demonstrated. Finally, CEA level was measured in 41 sera of patients with ovarian carcinoma by two radioimmunoassays, one using colonic CEA as tracer and standard and anti-colonic CEA serum, the other using ovarian CEA and anti-ovarian CEA serum: the values given by the two assays were highly correlated (rsub(s) = 0.8107), meaning that an organ specific assay for ovarian CEA is not needed. (Auth.)

  10. Improvements on Low Level Activity Gamma Measurements and X-ray Spectrometry at the CEA-MADERE Measurement Platform

    OpenAIRE

    Sergeyeva Victoria; Domergue Christophe; Destouches Christophe; Girard Jean Michel; Philibert Hervé; Bonora Jonathan; Thiollay Nicolas; Lyoussi Abdallah

    2016-01-01

    The CEA MADERE platform (Measurement Applied to DosimEtry in REactors) is a part of the Instrumentation Sensors and Dosimetry Laboratory (LDCI). This facility is dedicated to the specific activity measurements of solid and radioactive samples using Gamma and X-ray spectrometry. MADERE is a high-performance facility devoted to neutron dosimetry for experimental programs performed in CEA and for the irradiation surveillance programmes of PWR vessels. The MADERE platform is engaged in a continuo...

  11. CEA technical-economic activity report - Year 2014

    International Nuclear Information System (INIS)

    2015-01-01

    This report presents an assessment of activities undertaken by the CEA in the field of energy technique and economy during 2014. Technical-economic studies aims at contributing to national orientations on energy, at R and D program orientations, at highlighting and strengthening synergies between nuclear technologies and new energy technologies, and at strengthening the credibility of these technologies. After a presentation of the organisation of technique and economy within the CEA, of the involved bodies and departments, of the addressed themes (photovoltaic, wind, biomass and biofuels, hydrogen-based systems, mobility, electric systems and grids), the report presents studies performed in relationship with the national energy strategy and with energy scenarios, studies performed in the nuclear field (on fourth-generation reactors, on the front-end and back-end of the fuel cycle), studies performed in the field of new energy technologies and climate (hydrogen and storage, biofuels, climate, mobility, solar, electric systems). The next part addresses academic aspects, methodological studies and modelling studies. Contributions and participations to conferences, and publications are indicated

  12. OSIRIS Detectors

    Science.gov (United States)

    Joven, E.; Gigante, J.; Beigbeder, F.

    OSIRIS (Optical System for Imaging and Low-Resolution Integrated Spectroscopy) is an instrument designed to obtain images and low-resolution spectra of astronomical objects in the optical domain (from 365-1000 nm). It will be installed on Day One (2004) in the Nasmyth focus of the 10-m Spanish GTC Telescope. The mosaic is composed of two abuttable 2Kx4K CCDs to yield a total of 4Kx4K pixels, 15 μm/pixel, 0.1252 plate scale. The arrangement allows the linking of a classical ARC-GenII controller to a PMC frame-grabber, plugged into a VME-CPU card, where a RTOS (VxWorks from Wind River) is running. Some tests and results, carried out with a couple of MAT44-82 engineering grade devices at room temperature, are given.

  13. Scientific evaluation at the French Atomic Energy Commission (CEA). 2005-2006 annual report

    International Nuclear Information System (INIS)

    2006-01-01

    This report aims at presenting the scientific evaluation activities carried out at the CEA during the years 2005-2006. The evaluation system is described in detail. It comprises two aspects: the evaluation of the scientific policy implemented by the scientific Council and by the visiting committee of the CEA, and the evaluation of the laboratories, performed by a pool of 36 scientific councils. The evaluation by external and independent parties is the key point of this system. This document makes a status of the evaluations performed in 2005 and 2006. It presents a synthesis of the conclusions of the evaluation authorities. The actions implemented by the CEA to take into consideration the recommendations are also reported with the improvements noticed. The two topics examined by the scientific Committee and by the visiting committee were dealing with the energy domain, which is a strategic issue for the CEA. The examination of the researches on future nuclear reactors and on new energy technologies have shown the major role played by the CEA in the recent advances in these domains. About 95% of the laboratories activity was examined during the 2002-2005 period. The richness of the remarks and recommendations made by the scientific councils should allow the CEA to improve the quality and relevance of its research works. The start-up of the 2006-2009 evaluation cycle has been the occasion to modify the evaluation of some research domains in order to take into account the evolution of programs. The evaluation system of the CEA is highly consistent with the AERES principles. Its implementation, adapted to each type of activity (fundamental research, applied research, technological developments) allows the CEA to follow up a permanent improvement approach. (J.S.)

  14. The OSIRIS-REx laser altimeter (OLA): Development progress

    Science.gov (United States)

    Daly, M.; Barnouin, O.; Johnson, C.; Bierhaus, E.; Seabrook, J.; Dickinson, C.; Haltigin, T.; Gaudreau, D.; Brunet, C.; Cunningham, G.; Lauretta, D.; Boynton, W.; Beshore, E.

    2014-07-01

    Introduction: The NASA New Frontiers Origins Spectral Interpretation Resource Identification Security Regolith Explorer (OSIRIS-REx) mission will be the first to sample the B-type asteroid (101955) Bennu [1]. This asteroid is thought to be primitive and carbonaceous, and is probably closely related to CI and/or CM meteorites [2]. The OSIRIS-REx mission hopes to better understand both the physical and geochemical origin and evolution of carbonaceous asteroids through its investigation of Bennu. The OSIRIS-REx spacecraft will launch in September 2016, and arrive at Bennu two years later. The Canadian Space Agency is contributing a scanning lidar system known as the OSIRIS-REx Laser Altimeter (OLA), to the OSIRIS-REx Mission. The OLA instrument is part of suite of onboard instruments [3] including cameras (OCAMS) [4], a visible and near- infrared spectrometer (OVIRS) [5], a thermal emission spectrometer (OTES), and an X-ray imaging spectrometer (REXIS) [6]. OLA Objectives: The OLA instrument has a suite of scientific and mission operations purposes. At a global scale, it will update the shape and mass of Bennu to provide insights on the geological origin and evolution of Bennu, by, for example, further refining constraints on its bulk density. With a carefully undertaken geodesy campaign, OLA-based precision ranges, constraints from radio science (2-way tracking) data and stereo OCAMS images, it will yield broad-scale, quantitative constraints on any internal heterogeneity of Bennu and hence provide further clues to Bennu's origin and subsequent collisional evolution. OLA-derived global asteroid maps of slopes, elevation relative to the asteroid geoid, and vertical roughness will provide quantitative insights on how local-regional surfaces on Bennu evolved subsequent to the formation of the asteroid. In addition, OLA data and derived products support the assessment of the safety and sampleability of potential sample sites. At the sample-site scale, the OLA instrument

  15. Status of French reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ballagny, A. [Commissariat a l`Energie Atomique, Saclay (France)

    1997-08-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm{sup 3}. The OSIRIS reactor has already been converted to LEU. It will use U{sub 3}Si{sub 2} as soon as its present stock of UO{sub 2} fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU.

  16. Cutoff Values of Serum Carcinoembryonic Antigen (CEA) in Normal Korean Adults and Factors Influencing Serum CEA Level

    International Nuclear Information System (INIS)

    Kim, Jong Soon; Kim, Sun Wook; Chung, June Key; Lee, Dong Soo

    1994-01-01

    Carcinoembryonic Antigen is one of most frequently checked tumor markers in cancer management. We performed statistical analysis with serum CEA data of 2626 persons who received regular health examination and were thought to be free of active disease to determine the cutoff values of serum CEA level in normal Korean adults and to study the factors influencing serum CEA levels in normal subjects. 1) The cutoff values of serum CEA in normal Korean adults in general were 9.28 ng/ml for men, 5.90 ng/ml for women. 2) Serum CEA level was influenced by age, present smoking history, sex, and abnormal findings in chest X ray. 3) Serum CEA level had no correlation with the history of amount of alcohol consumption or obesity. 4) Cutoff values of serum CEA in normal Korean adults were tabulated according to age, sex, and smoking history. Serum CEA level was influenced by age, sex, present smoking history and abnormal findings in chest X ray and cutoff values of serum CEA were tabulated according to age, sex, and smoking history.

  17. Carcinoembryonic antigen (CEA) level, CEA ratio, and treatment outcome of rectal cancer patients receiving pre-operative chemoradiation and surgery

    International Nuclear Information System (INIS)

    Yang, Kai-Lin; Chang, Shih-Ching; Chu, Lee-Shing; Wang, Ling-Wei; Yang, Shung-Haur; Liang, Wen-Yih; Kuo, Ying-Ju; Lin, Jen-Kou; Lin, Tzu-Chen; Chen, Wei-Shone; Jiang, Jeng-Kae; Wang, Huann-Sheng

    2013-01-01

    To investigate serum carcinoembryonic antigen (CEA) as a prognostic factor for rectal cancer patients receiving pre-operative chemoradiotherapy (CRT). Between 2000 and 2009, 138 patients with advanced rectal cancer receiving CRT before surgery at our hospital were retrospectively classified into 3 groups: pre-CRT CEA <6 ng/ml (group L; n = 87); pre-CRT CEA ≥ 6 ng/ml and post-CRT CEA <6 ng/ml (group H-L; n = 32); and both pre- and post-CRT CEA ≥ 6 ng/ml (group H-H; n = 19). CEA ratio (defined as post-CRT CEA divided by pre-CRT CEA), post-CRT CEA level and other factors were reviewed for prediction of pathologic complete response (pCR). Five-year disease-free survival (DFS) was better in groups L (69.0%) and H-L (74.5%) than in group H-H (44.9%) (p = 0.024). Pathologic complete response was observed in 19.5%, 21.9% and 5.3% of groups L, H-L and H-H respectively (p = 0.281). Multivariate analysis showed that ypN stage and pCR were independent prognostic factors for DFS and that post-CRT CEA level was independently predictive of pCR. As a whole, post-CRT CEA <2.61 ng/ml predicted pCR (sensitivity 76.0%; specificity 58.4%). For those with pre-CRT CEA ≥6 ng/ml, post-CRT CEA and CEA ratio both predicted pCR (sensitivity 87.5%, specificity 76.7%). In patients with pre-CRT serum CEA ≥6 ng/ml, those with “normalized” CEA levels after CRT may have similar DFS to those with “normal” (<6 ng/ml) pre-CRT values. Post-CRT CEA level is a predictor for pCR, especially in those with pre-CRT CEA ≥6 ng/ml

  18. CEA 2005 annual report; CEA rapport annuel 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document is the 2005 activity report of the French atomic energy commission (CEA). The CEA is a main actor of nuclear research, development and innovation and is involved in three main domains: energy, defense/security, and information/health technologies thanks to high quality research works. With a manpower of 15000 researchers and collaborators with internationally acknowledged competences, the CEA is a driving force of industrial innovation and develops partnerships with French and European industries. It also warrants the perenniality of nuclear dissuasion. This report presents these different aspects of the CEA activities: 1 - defense-security: simulation program, opening to the scientific community, nuclear warheads, nuclear propulsion, cleansing of Rhone valley facilities, permanent monitoring of treaties respect, fight against terrorism; 2 - energy: optimization of the industrial park, advances in long lived radioactive wastes management, future nuclear systems, cleansing and dismantling integration, European nuclear energy research, new energy technologies; 3 - information and health technologies: major challenge of micro- and nano-technologies, key role of software technologies and complex systems; 4 - big research facilities opened to the scientific and industrial communities; 5 - scientific status: scientific evaluation process, prices and honors; 6 - programs support: revisited strategic control, confirmed simplification, active employment and training policy, teaching and training, technological valorization, international relations, communication, continuous quality approach, mastery of facilities safety, security, environmental control, a key-year for information systems. A financial report is attached to the document. (J.S.)

  19. Status of CEA reactor studies for a 200 kWe turbo electric space power system

    International Nuclear Information System (INIS)

    Carre, F.; Gervaise, F.; Proust, E.; Schwartz, J.P.; Tilliette, Z.; Vrillon, B.

    1986-01-01

    The present European ARIANE space program will expand after 1995 in the development of the large ARIANE 5 launch vehicle. Considering, that the range of power needs (50 to 400 kWe) and operation times required for the space missions planned after the year 2000, are relevant to a nuclear power system, the French Centre National d'Etudes Spatiales (CNES) invited in 1983 the Commissariat a l'Energie Atomique (CEA) to undertake preliminary studies on space power systems. The purpose of the present two year phase (mid 1984-mid 1986) is to identify key technologies for a space generator within the power range of interest and to estimate the development cost of such a project to be examined for commitment in 1986. This work mainly consists in the feasibility and cost assessment of a reference 200 kWe turboelectric space generator, selected for the maturity and availability of the conversion system and for its attractive specific mass compared to thermionics and thermoelectricity, considering the available radiator area afforded by the specific ARIANE 5 geometrical features. The system is basically composed of a fast neutron spectrum lithium cooled reactor, of a Brayton conversion loop and of a heat pipe radiator

  20. The planetary spatial data infrastructure for the OSIRIS-REx mission

    Science.gov (United States)

    DellaGiustina, D. N.; Selznick, S.; Nolan, M. C.; Enos, H. L.; Lauretta, D. S.

    2017-12-01

    The primary objective of the Origins, Spectral Interpretation, Resource Identification, and Security-Regolith Explorer (OSIRIS-REx) mission is to return a pristine sample of carbonaceous material from primitive asteroid (101955) Bennu. Understanding the geospatial context of Bennu is critical to choosing a sample-site and also linking the nature of the sample to the global properties of Bennu and the broader asteroid population. We established a planetary spatial data infrastructure (PSDI) support the primary objective of OSIRIS-REx. OSIRIS-REx is unique among planetary missions in that all remote sensing is performed to support the sample return objective. Prior to sampling, OSIRIS-REx will survey Bennu for nearly two years to select and document the most valuable primary and backup sample sites. During this period, the mission will combine coordinated observations from five science instruments into four thematic maps: deliverability, safety, sampleability, and scientific value. The deliverability map assesses the probability that the flight dynamics team can deliver the spacecraft to the desired location. The safety map indicates the probability that physical hazards are present at the sample-site. The sampleability map quantifies the probability that a sample can be successfully collected from the surface. Finally, the scientific value map shows the probability that the collected sample contains organics and volatiles and also places the sample site in a definitive geological context relative to Bennu's history. The OSIRIS-REx Science Processing and Operations Center (SPOC) serves as the operational PSDI for the mission. The SPOC is tasked with intake of all data from the spacecraft and other ground sources and assimilating these data into a single comprehensive system for processing and presentation. The SPOC centralizes all geographic data of Bennu in a relational database and ensures that standardization and provenance are maintained throughout proximity

  1. Control of the Saclay CEA's base nuclear installations - Inspection n. INS-2010-CEASAC-0006 31 May 2010-4 June 2010 - Safety management

    International Nuclear Information System (INIS)

    2010-01-01

    This document reports an inspection dedicated to safety management, and performed by the ASN (the French Nuclear Safety Authority) on several nuclear installations present on the CEA's Saclay site. The inspected installations have been the INBs (base nuclear installations) number 35 (STEL), 40 (Osiris), 49 (LHA), 50 (LECI), 77 (Poseidon) and 101 (Orphee), and four departments (CCSIMN, USL2TI, SP2S and DANS) involved in safety or in charge of it. The report describes the requested corrective actions about the quality of the internal diagnosis, about the follow-up of actions and directives, about internal authorizations, about the follow-up of commitments, about second level control, about the management of the return on experience, about interesting events, about the control of subcontractors. Some additional information requests are also formulated

  2. The great Cea actors

    International Nuclear Information System (INIS)

    Frejacques, C.

    1997-01-01

    With the Claude Frejacques life it is a Cea passage that we find. He began the studies on uranium isotope separation. He developed and saw to a successful conclusion these researches at Cea during twenty five years and extended his sphere of operations to the whole fuel cycle, from upstream to downstream. Director of research at the Cea, he was also D.G.R.S.T. director and during eight years President of the C.N.R.S. (N.C.)

  3. the JHR Material Testing Reactor

    International Nuclear Information System (INIS)

    Roure, C.; Cornu, B.; Berthet, B.; Simon, E.; Estre, N.; Guimbal, P.; Kinnunen, P.; Kotiluoto, P.

    2013-06-01

    The Jules Horowitz Reactor (JHR) is a European experimental reactor under construction in CEA Cadarache. It will be dedicated to material and fuel irradiation tests, and to medical isotopes production. Non-Destructive nuclear Examinations systems (NDE) will be implemented in pools to analyse the irradiated fuel or tested material in their supporting experimental irradiation devices extracted from the core or its immediate periphery. The Nuclear Measurement Laboratory (NML) of CEA Cadarache is working in collaboration with VTT (Technical Research Centre in Finland) in designing and developing NDE systems implementing gamma-ray spectroscopy and high energy X-ray imaging of the sample and irradiation device. CEA is also designing a neutron radiography system for which NML is working on the detection system. Design studies are performed with Monte Carlo transport codes and specific simulation tools developed by the NML for Xray and neutron imaging. (authors)

  4. French LEU fuel for research reactor with emphasis on the Osiris experience of core conversion and reactor operation with the new fuel

    International Nuclear Information System (INIS)

    Cerles, J.-M.

    1981-09-01

    One of the various activities carried out in France concerned with the design, fabrication and development of nuclear fuels was the development by the CEA of a plate type fuel (Caramel fuel). A Caramel fuel element is in the form of a plate consisting of two tight covering zircaloy sheets in which the UO 2 platelets are confined themselves within the network of a zircaloy grid. The plane geometry provides an effective means of overcoming the drawback of poor uranium oxide conductivity, and makes it possible to combine high specific power with low fuel temperature. The chief advantages of this fuel are the following: it is a very low enriched fuel. It can be used in research reactors demanding high volumetric powers and neutron fluxes, with a required enrichment significantly lower than 20% 235 U. The difference between the densities of UO 2 matrix and U-Al, 10.3 and 1.6 g/cm respectively, leads to a higher uranium charge, making it possible to reduce the enrichment to between 3 and 10%. Owing to fuel dispersion, any loss of tightness only puts a small amount of fissile material in contact with the coolant, thus limiting any contamination of the primary circuit. Another safety factor is the operating temperature, which is considerably lower than the temperature at which fission gases are liberated

  5. Shutdown channels and fitted interlocks in atomic reactors

    International Nuclear Information System (INIS)

    Furet, J.; Landauer, C.

    1968-01-01

    This catalogue consists of tables (one per reactor) giving the following information: number and type of detectors, range of the shutdown channels, nature of the associated electronics, thresholds setting off the alarms, fitted interlocks. These cards have been drawn up with a view to an examination of the reactors safety by the 'Reactor Safety Sub-Commission', they take into account the latest decisions. The reactors involved in this review are: Azur, Cabri, Castor-Pollux, Cesar-Marius-2, Edf-2, EL3, EL4, Eole, G1, G2-G3, Harmonie, Isis, Masurca, Melusine, Minerve, Osiris, Pegase, Peggy, PAT, Rapsodie, SENA, Siloe, Siloette, Triton-Nereide, and Ulysse. (authors) [fr

  6. Dismantling and waste management: CEA's strategy and research programs

    International Nuclear Information System (INIS)

    Behar, C.

    2012-01-01

    There are 3 main dismantling operations in CEA. First, the dismantling of the UP1 facility in the Marcoule site. UP1 was a reprocessing plant of nuclear fuels that operated from 1958 to 1997 and is now the biggest dismantling operation in the world. Its dismantling operation follows a 6-step scheme that will end in 2050. Secondly, the Passage project on the Grenoble site that concerns the dismantling of 3 research reactors (Siloette, Melusine and Siloe), of a laboratory dedicated to the analysis of active materials (Lama) and of a station for the processing of waste (Sted). Thirdly the Aladin project that concerns the installations of the Fontenay-aux-Roses site. The dismantling operations are complex because all the first research programs on high activity chemistry and on transuranium elements were performed in Fontenay-aux-Roses facilities and because ancient activities have to leave a clean place to be replaced by new ones. The radioactive waste produced by CEA enter the flow of waste that is normally processed and managed by ANDRA. Only high-activities waste have not yet a definitive solution, they are stored in waiting the opening of a geological repository. CEA leads research programs on the separation and transmutation of minor actinides and on the long-term behaviour of waste packages put in deep geological layers. (A.C.)

  7. CEA Annual report 2007

    International Nuclear Information System (INIS)

    2007-01-01

    The CEA, a prominent player in research development and innovation, is active in three main domains: energy, health care and information technology, defense and security. This annual report presents the CEA activities for the year 2007 in these three main areas: science and technology working for nuclear deterrence and global security, the energies without greenhouse effect gases emission against the climatic change, researches in the information sciences and technologies for a better communication and health. The CEA safety, organization, communication and international relations are also presented. (A.L.B.)

  8. [Significance of CEA in gastric and colorectal cancer].

    Science.gov (United States)

    Uehara, K; Miyamoto, Y; Izuo, M; Shiozaki, H; Aiba, S; Matsumoto, H

    1985-04-01

    The determination of serum CEA (Sandwich method) and CEA staining (PAP method) of excised specimens were performed in patients with gastric or colorectal cancer, and the biological characteristics of each cancer and the factors to increase serum CEA were studied with the following results: As colonic cancer has strong CEA productivity, serum CEA can be useful for the detection of cancer, and especially effective for the postoperative observation. Gastric cancer has weak CEA productivity, and serum CEA is not so useful in the detection of cancer and the judgement of resectability. The CEA positive rate of tissue with CEA staining was 80% in gastric cancer, 100% in colonic cancer, and were nearly equal to the CEA positive rate of serum in the group of terminal stage. In the mode of CEA staining of cancerous cells, IV type was observed most frequently in gastric cancer, and I type in colonic cancer. Among the resected cases showing more than 7ng/ml serum CEA, differentiated type, lymph node metastasis (+), the degree of tissue staining with CEA staining, the mode of cell staining O or I type in gastric cancer and I type in colonic cancer were observed in common.

  9. Licensing procedures and safety criteria for research reactors in France

    International Nuclear Information System (INIS)

    Berry, J.L.; Lerouge, B.

    1980-11-01

    This paper summarizes the recent evolution of the French research reactor capacity, describes the licensing process, the main safety criteria which are taken into consideration, and associated safety research. Some of the existing facilities underwent important modifications to comply with more severe safety criteria, increase the experimental capabilities or qualify new low-enrichment fuels for research reactors. At the end, a few considerations are given to the consequences of the Osiris core conversion

  10. OSiRIS: a distributed Ceph deployment using software defined networking for multi-institutional research

    Science.gov (United States)

    McKee, Shawn; Kissel, Ezra; Meekhof, Benjeman; Swany, Martin; Miller, Charles; Gregorowicz, Michael

    2017-10-01

    We report on the first year of the OSiRIS project (NSF Award #1541335, UM, IU, MSU and WSU) which is targeting the creation of a distributed Ceph storage infrastructure coupled together with software-defined networking to provide high-performance access for well-connected locations on any participating campus. The projects goal is to provide a single scalable, distributed storage infrastructure that allows researchers at each campus to read, write, manage and share data directly from their own computing locations. The NSF CC*DNI DIBBS program which funded OSiRIS is seeking solutions to the challenges of multi-institutional collaborations involving large amounts of data and we are exploring the creative use of Ceph and networking to address those challenges. While OSiRIS will eventually be serving a broad range of science domains, its first adopter will be the LHC ATLAS detector project via the ATLAS Great Lakes Tier-2 (AGLT2) jointly located at the University of Michigan and Michigan State University. Part of our presentation will cover how ATLAS is using the OSiRIS infrastructure and our experiences integrating our first user community. The presentation will also review the motivations for and goals of the project, the technical details of the OSiRIS infrastructure, the challenges in providing such an infrastructure, and the technical choices made to address those challenges. We will conclude with our plans for the remaining 4 years of the project and our vision for what we hope to deliver by the projects end.

  11. OSIRIS-REx Touch-And-Go (TAG) Navigation Performance

    Science.gov (United States)

    Berry, Kevin; Antreasian, Peter; Moreau, Michael C.; May, Alex; Sutter, Brian

    2015-01-01

    The Origins Spectral Interpretation Resource identification Security Regolith Explorer (OSIRIS-REx) mission is a NASA New Frontiers mission launching in 2016 to rendezvous with the near-Earth asteroid (101955) Bennu in late 2018. Following an extensive campaign of proximity operations activities to characterize the properties of Bennu and select a suitable sample site, OSIRIES-REx will fly a Touch-And-Go (TAG) trajectory to the asteroid's surface to obtain a regolith sample. The paper summarizes the mission design of the TAG sequence, the propulsive required to achieve the trajectory, and the sequence of events leading up to the TAG event. The paper will summarize the Monte-Carlo simulation of the TAG sequence and present analysis results that demonstrate the ability to conduct the TAG within 25 meters of the selected sample site and +-2 cms of the targeted contact velocity. The paper will describe some of the challenges associated with conducting precision navigation operations and ultimately contacting a very small asteroid.

  12. OSIRI-REx Touch and Go (TAG) Navigation Performance

    Science.gov (United States)

    Berry, Kevin; Antreasian, Peter; Moreau, Michael C.; May, Alex; Sutter, Brian

    2015-01-01

    The Origins Spectral Interpretation Resource Identification Security Regolith Explorer (OSIRIS-REx) mission is a NASA New Frontiers mission launching in 2016 to rendezvous with the near-Earth asteroid (101955) Bennu in late 2018. Following an extensive campaign of proximity operations activities to characterize the properties of Bennu and select a suitable sample site, OSIRIS-REx will fly a Touch-And-Go (TAG) trajectory to the asteroid's surface to obtain a regolith sample. The paper summarizes the mission design of the TAG sequence, the propulsive maneuvers required to achieve the trajectory, and the sequence of events leading up to the TAG event. The paper also summarizes the Monte-Carlo simulation of the TAG sequence and presents analysis results that demonstrate the ability to conduct the TAG within 25 meters of the selected sample site and 2 cm/s of the targeted contact velocity. The paper describes some of the challenges associated with conducting precision navigation operations and ultimately contacting a very small asteroid.

  13. Safety and authorizations relating to the use of new fuel in research reactors

    International Nuclear Information System (INIS)

    Niel, J.-C.; Abou Yehia, H.

    1999-01-01

    After giving a brief reminder of the procedure applied in France for granting licences to modify research reactors, we outline in this paper the main safety aspects associated with using new fuel in these reactors. Finally, by way of an example, we focus on the procedure followed for converting the cores of the OSIRIS (70 MW) and ISIS (700 kW) reactors to U 3 Si 2 Al fuel and the conclusions of the corresponding safety assessments. (author)

  14. OSIRIS, a MTR adapted and well fitted to LEU utilization qualification and development

    International Nuclear Information System (INIS)

    Barnier, M.; Beylot, J.P.

    1984-01-01

    The MTR OSIRIS has been successfully operated for 4 years using the ''Caramel'' low enriched uranium dioxyde fuel for the whole core loading. In the first part we examine the performance and operating experience obtained up to the present time with ''Caramel''. In a second part the paper discusses the results of the calculations for a complete OSIRIS core loaded with 20 % silicide fuel and makes a comparison with UAl 93 % and ''Caramel'' 7 % fuels. (author)

  15. Retrieval of vertical concentration profiles from OSIRIS UV-visible limb spectra

    International Nuclear Information System (INIS)

    Strong, K.; Joseph, B.M.; Dosanjh, R.; McDade, I.C.; McLinden, C.A.; McConnell, J.C.; Stegman, J.; Murtagh, D.P.; Llewellyn, E.J.

    2002-01-01

    The OSIRIS instrument, launched on the Odin satellite in February 2001, includes an optical spectrograph that will record UV-visible spectra of sunlight scattered from the limb over a range of tangent heights. These spectra will be used to retrieve vertical profiles of ozone, NO 2 , OC1O, BrO, NO 3 , O 2 , and aerosols, for the investigation of both stratospheric and mesospheric processes, particularly those related to ozone chemistry. In this work, the retrieval of vertical profiles of trace-gas concentrations from OSIRIS limb-radiance spectra is described. A forward model has been developed to simulate these spectra, and it consists of a single-scattering radiative-transfer model with partial spherical geometry, trace-gas absorption, Mic scattering by stratospheric aerosols, a Lambertian surface contribution, and OSIRIS instrument response and noise. Number-density profiles have been retrieved by using optimal estimation (OE) to combine an a priori profile with the information from sets of synthetic 'measurements'. For ozone, OE has been applied both to limb radiances at one or more discrete wavelengths and to effective-column abundances retrieved over a broad spectral range using differential optical absorption spectroscopy (DOAS). The results suggest that, between 15 and 35 km, ozone number densities can be retrieved to 10% accuracy or better on 1 and 2 km grids and to 5% on a 5 km grid. The combined DOAS-OE approach has also been used to retrieve NO 2 number densities, yielding 13% accuracy or better for altitudes from 18 to 36 km (in a 2 km grid. Differential optical absorption spectroscopy - optimal estimation retrievals of BrO and OC1O reproduce the true profiles above 15 km in the noise-free case, but the quality of the retrievals is highly sensitive to noise on the simulated OSIRIS spectra because of the weak absorption of these two gases. The development of inversion methods for the retrieval of trace-gas concentrations from OSIRIS spectra is continuing

  16. On use of ZPR research reactors and associated instrumentation and measurement methods for reactor physics studies

    Energy Technology Data Exchange (ETDEWEB)

    Chauvin, J.P. [CEA,DEN, DER, SPEX, Experimental Physics Service, Cadarache, F-13108 St-Paul-Lez-Durance (France); Blaise, P. [CEA, DEN, DER, SPEX Experimental Programs Laboratory, Cadarache, F-13108 St-Paul-Lez-Durance (France); Lyoussi, A. [CEA, DEN, DER, Instrumentation Sensors and Dosimetry Laboratory, Cadarache, F-13108 St-Paul-Lez-Durance (France)

    2015-07-01

    The French atomic and alternative energies -CEA- is strongly involved in research and development programs concerning the use of nuclear energy as a clean and reliable source of energy and consequently is working on the present and future generation of reactors on various topics such as ageing plant management, optimization of the plutonium stockpile, waste management and innovative systems exploration. Core physics studies are an essential part of this comprehensive R and D effort. In particular, the Zero Power Reactor (ZPR) of CEA: EOLE, MINERVE and MASURCA play an important role in the validation of neutron (as well photon) physics calculation tools (codes and nuclear data). The experimental programs defined in the CEA's ZPR facilities aim at improving the calculation routes by reducing the uncertainties of the experimental databases. They also provide accurate data on innovative systems in terms of new materials (moderating and decoupling materials) and new concepts (ADS, ABWR, new MTR (e.g. JHR), GENIV) involving new fuels, absorbers and coolant materials. Conducting such interesting experimental R and D programs is based on determining and measuring main parameters of phenomena of interest to qualify calculation tools and nuclear data 'libraries'. Determining these parameters relies on the use of numerous and different experimental techniques using specific and appropriate instrumentation and detection tools. Main ZPR experimental programs at CEA, their objectives and challenges will be presented and discussed. Future development and perspectives regarding ZPR reactors and associated programs will be also presented. (authors)

  17. The dismantling of nuclear installations in the Grenoble CEA centre - Press book 2013

    International Nuclear Information System (INIS)

    Laveissiere, Stephane; Coronini, Vincent

    2013-01-01

    After having outlined the importance of the project for the Grenoble CEA centre, this document presents the objectives, issues and challenges of dismantling activities performed on various nuclear installations located in the CEA centre of Grenoble. Objectives are presented in terms of agenda, predicted production of radioactive wastes, budget, personnel and steering committee. The various nuclear installations are presented: experimental reactors (Melusine, Siloe, Siloette), LAMA (laboratory of analysis of active materials), STED (station for the treatment of effluents and wastes). The safety and protection of workers is addressed in terms of protection and monitoring measures, and of exposure to radiations. The next part deals with the monitoring of the environment (actors, history of control of the centre's releases, control points, releases, atmosphere monitoring, and hydrological monitoring). A second part presents the global strategy of the CEA for its activities of sanitation and nuclear dismantling: present operations, dismantling activities in Fontenay-aux-Roses and in Marcoule, economic organization, contribution of advanced technology in radiological measurement and control, simulation and modelling, decontamination techniques, cutting operations, and remotely controlled operations

  18. Overview of the CEA R and D support to generation IV nuclear energy systems

    International Nuclear Information System (INIS)

    Carre, Frank; Anzieu, Pascal; Billot, Philippe; Brossard, Philippe; Fiorini, Gian-Luigi

    2004-01-01

    As a result of an early technology road-map performed at the end of 2000, the CEA selected a sequenced development of advanced gas cooled high temperature nuclear systems as main focus for its R and D programme on future nuclear energy systems. The selection of this research objectives originates both from the significance of fast neutrons and high temperature for nuclear energy to meet the needs anticipated beyond 2020/2030, and from the significant common R and D pathway that supports both medium term industrial projects and more advanced versions of gas cooled reactors. The first step of the 'Gas Technology Path' aims to support the development of a modular HTR likely to meet international market needs around 2020. The second step is a Very High Temperature Reactor (> 950 deg. C) to efficiently produce, among others, hydrogen though thermo-chemical water splitting or to generate electricity with an efficiency above 50%. The third step of the Path is a Gas Fast Reactor that features a fast-spectrum helium-cooled reactor and closed fuel cycle, with a direct-cycle helium turbine for electricity production and full recycle of actinides. The paper succinctly presents the R and D program launched in 2001 by the CEA with industrial partners on the 'Gas Technology Path', which is destined to become the contribution of France to the development of the VHTR and the GFR within the next phase of the Generation IV Forum

  19. Overview of the CEA R and D support to generation IV nuclear energy systems

    Energy Technology Data Exchange (ETDEWEB)

    Carre, Frank; Anzieu, Pascal; Billot, Philippe; Brossard, Philippe; Fiorini, Gian-Luigi

    2004-07-01

    As a result of an early technology road-map performed at the end of 2000, the CEA selected a sequenced development of advanced gas cooled high temperature nuclear systems as main focus for its R and D programme on future nuclear energy systems. The selection of this research objectives originates both from the significance of fast neutrons and high temperature for nuclear energy to meet the needs anticipated beyond 2020/2030, and from the significant common R and D pathway that supports both medium term industrial projects and more advanced versions of gas cooled reactors. The first step of the 'Gas Technology Path' aims to support the development of a modular HTR likely to meet international market needs around 2020. The second step is a Very High Temperature Reactor (> 950 deg. C) to efficiently produce, among others, hydrogen though thermo-chemical water splitting or to generate electricity with an efficiency above 50%. The third step of the Path is a Gas Fast Reactor that features a fast-spectrum helium-cooled reactor and closed fuel cycle, with a direct-cycle helium turbine for electricity production and full recycle of actinides. The paper succinctly presents the R and D program launched in 2001 by the CEA with industrial partners on the 'Gas Technology Path', which is destined to become the contribution of France to the development of the VHTR and the GFR within the next phase of the Generation IV Forum.

  20. OSIRIS-REx Touch-And-Go (TAG) Mission Design and Analysis

    Science.gov (United States)

    Berry, Kevin; Sutter, Brian; May, Alex; Williams, Ken; Barbee, Brent W.; Beckman, Mark; Williams, Bobby

    2013-01-01

    The Origins Spectral Interpretation Resource Identification Security Regolith Explorer (OSIRIS-REx) mission is a NASA New Frontiers mission launching in 2016 to rendezvous with the near-Earth asteroid (101955) 1999 RQ36 in late 2018. After several months in formation with and orbit about the asteroid, OSIRIS-REx will fly a Touch-And-Go (TAG) trajectory to the asteroid s surface to obtain a regolith sample. This paper describes the mission design of the TAG sequence and the propulsive maneuvers required to achieve the trajectory. This paper also shows preliminary results of orbit covariance analysis and Monte-Carlo analysis that demonstrate the ability to arrive at a targeted location on the surface of RQ36 within a 25 meter radius with 98.3% confidence.

  1. Research and development program for PWR safety at the CEA reactor thermal hydraulics laboratories

    International Nuclear Information System (INIS)

    Bernard, M.

    1995-01-01

    Since the start of the French electronuclear program, the three partners Fermate, EDF and Cea (DRN and IPSN) have devoted considerable effort to research and development for safety issues. In particular an important program on thermal hydraulics was initiated at the beginning of the seventies. It is illustrated by the development of the CATHARE thermalhydraulic safety code which includes physical models derived from a large experimental support program and the construction of the BETHSY integral facility which is aimed to assess both the CATHARE code and the physical relevance of the accident management procedures to be applied on reactors. The state of the art on this program is described with particular emphasis on the capabilities and the assessment of the last version of CATHARE and the lessons drawn from 50 BETHSY tests performed so far. The future plans for safety research cover the following strategy: - to solve the few problems identified on present computing tools and extend the assessment - to solve the few problems identified on present computing tools and extend the assessment - to perform safety studies on the basis of plant operation feedback - to contribute to treating the safety issues related to the future reactors and in particular the case of severe accidents which have to be taken into account from the design stage. The program on severe accidents is aimed to support the design studies performed by the industrial partners and to provide computing tools which model the various phases of severe accidents and will be validated on experiments performed with real and simulating materials. The main lines of the program are: - the development of the TOLBIAC 3D code for the thermal hydraulics of core melt pools, which will be validated against the Bali experiment presently under construction - the Sultan experiment, to study the capability of cooling by external flooding of the reactor vessel - the development of the MC-3D code for core melt

  2. Construction of Research Reactors for Gen 3 and Gen 4 Reactors Development

    International Nuclear Information System (INIS)

    Behar, Christophe

    2014-01-01

    Christophe Behar, Director of the Nuclear Energy Division at CEA, detailed the different kind of research reactors and the issues in term of investment, use, side application such as the medical isotopes production

  3. Angiotomografía computerizada, colgajos de perforante, cirujano y OsiriX Computed tomography angiography, perforator flaps, surgeon and OsiriX

    Directory of Open Access Journals (Sweden)

    M. Rodríguez-Vegas

    2013-03-01

    Full Text Available Desde la introducción de la transferencia cutánea basada en perforantes, la angiotomografía computerizada ha emergido como una técnica de gran valor en la planificación preoperatoria de los colgajos de perforante. Sin embargo, parece probable que el aprovechamiento de la técnica sea menor del deseable. Evaluamos, a través de la experiencia en 144 pacientes, la utilidad del visor gratuito de imágenes DICOM OsiriX para Mac en la planificación preoperatoria de los colgajos de perforante con tres objetivos: 1 ampliar los conocimientos actuales relacionados con la aplicación de la angiotomografía computerizada en la planificación preoperatoria de los colgajos de perforante, 2 evaluar la aplicación OsiriX en el post-procesamiento de imágenes en la planificación preoperatoria de colgajos de perforante y 3 evaluar el rendimiento obtenible de la angiotomografía considerando que el postprocesamiento es realizado por un cirujano (no especialista en Radiodiagnóstico. La experiencia permite afirmar que el postprocesamiento de las imágenes DICOM por el cirujano con la aplicación Osirix permite habitualmente evaluar de manera adecuada diversas estructuras y parámetros de gran interés en la cirugía de colgajos de perforante: 1 arteria principal, origen de la perforante, 2 diámetro de arteria y vena/s en el hipotético sitio de anastomosis microquirúrgica, 3 recorrido y patrón de ramificación del pedículo del colgajo, 4 disposición de la perforante en la grasa subcutánea (teórico eje de diseño del colgajo, 5 medición del grosor cutáneo en el punto de perforación de la fascia profunda por la rama perforante (teórico grosor de colgajo, 6 medición de la distancia entre el punto de perforación de la fascia profunda por la rama perforante y el origen de la arteria principal (teórica longitud máxima posible de pedículo y 7 medición del diámetro, en el punto de perforación de la fascia profunda, de la perforante. En

  4. Review on use of neutron radiography at Saclay Nuclear Research Centre

    Energy Technology Data Exchange (ETDEWEB)

    Bayon, G [Saclay Nuclear Research Centre DRE/SRO, Gif-sur-Yvette (France)

    1996-11-01

    The Commissariat a l`Energie Atomique (CEA) operates three research reactors at Saclay. Each of them is equipped with a Neutron Radiology facility. Osiris is involved in studies of nuclear fuel rod behaviour during accidental events. The underwater NR facility allows to obtain images of the rods before and after power ramp. The Orphee installation is devoted to industrial application of NR including non destructive testing and real time imaging. The main activity concerns the examination of the pyrotechnic devices of the Ariane launcher programmes. Other areas of interest are also described. (author) 2 figs., 1 tab., 5 refs.

  5. Review on use of neutron radiography at Saclay Nuclear Research Centre

    International Nuclear Information System (INIS)

    Bayon, G.

    1996-01-01

    The Commissariat a l'Energie Atomique (CEA) operates three research reactors at Saclay. Each of them is equipped with a Neutron Radiology facility. Osiris is involved in studies of nuclear fuel rod behaviour during accidental events. The underwater NR facility allows to obtain images of the rods before and after power ramp. The Orphee installation is devoted to industrial application of NR including non destructive testing and real time imaging. The main activity concerns the examination of the pyrotechnic devices of the Ariane launcher programmes. Other areas of interest are also described. (author) 2 figs., 1 tab., 5 refs

  6. Fast wave current drive in reactor scale tokamaks

    International Nuclear Information System (INIS)

    Moreau, D.

    1992-01-01

    The IAEA Technical Committee Meeting on Fast Wave Current Drive in Reactor Scale Tokamaks, hosted by the Commissariat a l'Energie Atomique (CEA), Departement de Recherches sur la Fusion Controlee (Centres d'Etudes de Cadarache, under the Euratom-CEA Association for fusion) aimed at discussing the physics and the efficiency of non-inductive current drive by fast waves. Relevance to reactor size tokamaks and comparison between theory and experiment were emphasized. The following topics are described in the summary report: (i) theory and modelling of radiofrequency current drive (theory, full wave modelling, ray tracing and Fokker-Planck calculations, helicity injection and ponderomotive effects, and alternative radio-frequency current drive effects), (ii) present experiments, (iii) reactor applications (reactor scenarios including fast wave current drive; and fast wave current drive antennas); (iv) discussion and summary. 32 refs

  7. Reactor Neutrino Detection for Non Proliferation with the NUCIFER Experiment

    Energy Technology Data Exchange (ETDEWEB)

    Bouvet, L. [CEA, Centre de Saclay, IRFU, Gif-sur-Yvette, (France); Bouvier, S.; Bui, V. M. [Laboratoire Subatech, Ecole des Mines, Nantes Cedex 3 (France); others, and

    2012-06-15

    Neutrinos are the most abundant matter particles in the Universe. Thoroughly investigated in basic science, the neutrino field is now delivering first applications to the monitoring of nuclear reactors. The neutrinos are emitted in the decay chain of the fission products; therefore measuring their flux provides real-time information, directly related to the fission process occurring in the reactor core. Because of the very weak interaction of neutrinos with matter a neutrino detector can stand outside the core containment vessel and provide a non-intrusive and inherently tamper resistant measurement. After a brief review of the existing data and worldwide projects, we present the NUCIFER experiment. The active part of the detector is a tank filled up with one ton of Gadolinium-doped liquid scintillator. Sixteen photomultiplier tubes, isolated from the liquid by an acrylic buffer, read out the light produced by the interaction of a neutrino with the protons of the liquid. The tank is surrounded by plastic scintillator plates to veto the cosmic rays. Then polyethylene and lead shielding suppress the background coming from external neutrons and gamma rays respectively. The NUCIFER detector has been designed for an optimal compromise between the detection performances and the specifications of operation in a safeguards regime. Its global footprint is 2.8 m x 2.8 m and it can monitor remotely the nuclear power plant thermal power and Plutonium content with very little maintenance on years scale. The experiment is currently installed near the OSIRIS research reactor (70 MWth) at CEA, in Saclay, France. First data are expected by May 2012. This work is done in contact with the IAEA/SGTN division that is currently investigating the potentiality of neutrinos as a novel safeguards tool. A dedicated working group has been created in 2010 to coordinate the simulation effort of various reactor types as well as the development of dedicated detectors and define and eventually

  8. In-pile observation of gas release from sodium-joint carbide pins irradiated in Osiris

    International Nuclear Information System (INIS)

    Colin, M.; Faugere, J.L.; Rouault, J.

    1978-01-01

    Gas release is studied in three sodium-joint carbide pins irradiated in the reactor Osiris at a nominal linear power of 900 W/cm to burn-ups ranging from 4 to 13%. The overall activity, stable gases and radioactive gases are measured. It is found that most of the gas is released in busts, that the release of stable gases speeds up sharply after an incubation time, that the initial bursts are very large and that for each mode of release observed and for each class of nuclide the radioactive gases follow a law R/B=A/lambda.n. An attempt is made to interpret the results in terms of either the formation of gas bubbles in the sodium joint, the existence of a large bubble above the fissile column or the simultaneous release of a large number of smaller bubbles [fr

  9. CEA - Annual report 2006; CEA - Rapport annuel 2006

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    The CEA, a prominent player in research development and innovation, is active in 3 main areas: energy, health care and information technology and defense and security. This annual report presents the CEA activity for the year 2006 in these three main areas: Science and technology working for nuclear deterrence and global security (the simulation programs, the nuclear warheads, the nuclear propulsion, the decommissioning, the fighting against nuclear proliferation and monitoring international treaties, the global security); health and information technology (micro and nano technologies and systems); energy from nuclear fission and fusion and other technologies that do not emit greenhouse gases (progress for the nuclear industry, sustainable management of radioactive materials and waste, nuclear systems of the future, new energy technologies). (A.L.B.)

  10. OSIRIS: a runge kutta solver of systems of ordinary differential equations

    International Nuclear Information System (INIS)

    Collin, M.; Schett, A.

    1983-12-01

    The Code OSIRIS (Order and Step Idently Adjusting Runge-Kutta Integrator of Systems) has been developed on the basis of both explicit as well as implicit Runge-Kutta processes of various orders: 4(5), 7(8), 8(9), 10 for explicit processes and 4 and 6 for implicit processes of the Rosenbrock type. This permits an optimization of the integration procedure by choosing the appropriate type of Runge-Kutta methods (explicit or implicit) and by adjusting dynamically the order of the process as well as the step-size. The performance of the Code OSIRIS is demonstrated by some representative examples and is compared with the Code GEAR which is applying multistep methods

  11. Reagents for radioimmunological determination of carcinoembryonic antigen (CEA)

    International Nuclear Information System (INIS)

    Albert, Z.; Balbierz, H.; Breberowicz, J.

    1978-01-01

    The work was undertaken to prepare the reagents for carcinoembryonic antigen (CEA) radioimmunoassay with double antibody method. The CEA standard of high immunoreactivity was prepared and purified. The purified CEA was used for immunozation of goats. The goat anti - CEA sera were received. IgG fraction from normal goat serum was purified and used for the production of horse anti-goat IgG serum which was then used in the radioimmunoassay of CEA. The labelling of CEA with iodine-125 has been carried out be means of the enzymatic method.(Z.R.)

  12. CEA sustainable development report 2007

    International Nuclear Information System (INIS)

    2007-01-01

    The CEA, a prominent player in research development and innovation, is active in three main domains: energy, health care and information technology, defense and security. This annual report presents the CEA activities in the domain of the sustainable development. The first part is devoted to the environment preservation policy (energy, water, air, chemistry, wastes, transport, buildings). The second part shows the dynamic governance in the domain of the risks management. The last part presents the CEA activities of research for the sustainable development. (A.L.B.)

  13. Radioimmunodetection of colorectal cancer, using anti-CEA monoclonal antibodies

    International Nuclear Information System (INIS)

    Murayama, Hiroki; Watanabe, Tadashi; Tadokoro, Masanori; Takagi, Hiroshi; Sakuma, Sadayuki; Sakamoto, Junichi.

    1989-01-01

    Aiming at radioimmunodetection of colorectal cancer, anti-CEA monoclonal antibodies (CEA102) were produced by immunization with purified CEA. CEA102 showed high specificity with clorectal cancer by mixed hemadsorption assay and immunoperoxidase technique. The antigen detected by CEA102 was confirmed to be carcinoembryonic antigen (CEA) and its molecular weight was estimated to be ca. 180,000 by biochemical analysis. The in vivo study using nude mice grafted a human colorectal cancer or a human malignant melanoma showed greater accumulation of 125 I-labeled CEA102 in CEA-positive colorectal cancer than in nude mouse tissues and CEA-negative malignant melanoma. Moreover we successfully obtained scans with good localization of the grafted colorectal cancer on FCR (Fuji Computed Radiography). Using 131 I-labeled CEA102 liver metastasis in the patient with colorectal cancer was successfully detected by external scanning with γ-camera. These results suggest that radiolabeled CEA102 is useful for the detection of colorectal cancer. (author)

  14. Spectral Characterization of Analog Samples in Anticipation of OSIRIS-REx's Arrival at Bennu

    Science.gov (United States)

    Donaldson Hanna, K. L.; Schrader, D. L.; Bowles, N. E.; Clark, B. E.; Cloutis, E. A.; Connolly, H. C., Jr.; Hamilton, V. E.; Keller, L. P.; Lauretta, D. S.; Lim, L. F.; hide

    2017-01-01

    NASA's Origins, Spectral Interpretation, Resource Identification, and Security-Regolith Explorer (OSIRIS-REx) mission successfully launched on September 8th, 2016. During its rendezvous with near-Earth asteroid (101955) Bennu beginning in 2018, OSIRIS-REx will characterize the asteroid's physical, mineralogical, and chemical properties in an effort to globally map the properties of Bennu, a primitive carbonaceous asteroid, and choose a sampling location]. In preparation for these observations, analog samples were spectrally characterized across visible, near- and thermal-infrared wavelengths and were used in initial tests on mineral-phase-detection and abundance-determination software algorithms.

  15. The French approach through the SMR consortium (CEA, EDF, AREVA, DCNS)

    International Nuclear Information System (INIS)

    Chenais, J.; Diet, A.; Grondin, Y.; Perrier, S.

    2014-01-01

    The SMR (Small Modular Reactor) is a new range of nuclear reactors characterized by a low output power (less than 300 MWe) and a standardized modular factory-based construction. Moderate capital costs make this type of reactor very attractive for medium-size power utilities or small countries. A consortium made around the CEA and its industrial partners (EDF, AREVA and DCNS) has performed economic and technical feasibility studies. It appears that the competitiveness of SMR require power production costs around 100 euros/MWh and that SMR will be based on PWR technology with a power output of 150 MWe per unit. 2 types of SMR are proposed: a terrestrial unit and an immersed unit. The concept of the immersed SMR, called Flexblue, is based on an unlimited access to a cold sink (the ocean) and a complete modularity. In both types the standard of safety appears to be high. (A.C.)

  16. CEA - Risk control report 2014

    International Nuclear Information System (INIS)

    Verwaerde, Daniel; Bonnevie, Edwige; Maillot, Bernard

    2015-06-01

    After introductory presentations by CEA managers in charge of risk management and controls, this document presents and comments the actions undertaken by the CEA and the obtained results in terms of risk management in different fields: environment protection and control, facilities safety, health and radiation protection, transport of hazardous materials, waste management, sites protection, installations and assets, emergency response, legal risk management, internal inspections and audits. Other topics are addressed like the presentation of the risk control sector, and the role of the CEA in the relationship between research and industry

  17. Rapid development of image analysis research tools: Bridging the gap between researcher and clinician with pyOsiriX.

    Science.gov (United States)

    Blackledge, Matthew D; Collins, David J; Koh, Dow-Mu; Leach, Martin O

    2016-02-01

    We present pyOsiriX, a plugin built for the already popular dicom viewer OsiriX that provides users the ability to extend the functionality of OsiriX through simple Python scripts. This approach allows users to integrate the many cutting-edge scientific/image-processing libraries created for Python into a powerful DICOM visualisation package that is intuitive to use and already familiar to many clinical researchers. Using pyOsiriX we hope to bridge the apparent gap between basic imaging scientists and clinical practice in a research setting and thus accelerate the development of advanced clinical image processing. We provide arguments for the use of Python as a robust scripting language for incorporation into larger software solutions, outline the structure of pyOsiriX and how it may be used to extend the functionality of OsiriX, and we provide three case studies that exemplify its utility. For our first case study we use pyOsiriX to provide a tool for smooth histogram display of voxel values within a user-defined region of interest (ROI) in OsiriX. We used a kernel density estimation (KDE) method available in Python using the scikit-learn library, where the total number of lines of Python code required to generate this tool was 22. Our second example presents a scheme for segmentation of the skeleton from CT datasets. We have demonstrated that good segmentation can be achieved for two example CT studies by using a combination of Python libraries including scikit-learn, scikit-image, SimpleITK and matplotlib. Furthermore, this segmentation method was incorporated into an automatic analysis of quantitative PET-CT in a patient with bone metastases from primary prostate cancer. This enabled repeatable statistical evaluation of PET uptake values for each lesion, before and after treatment, providing estaimes maximum and median standardised uptake values (SUVmax and SUVmed respectively). Following treatment we observed a reduction in lesion volume, SUVmax and SUVmed for

  18. Decontamination and dismantling at the CEA; L'assainissement et le demantelement au CEA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-07-01

    This document presents the dismantling policy at the CEA (French Research Center on the atomic energy), the financing of the decontamination and the dismantling, the regulatory framework, the knowledge and the technology developed at the CEA, the radiation protection, the environment monitoring and the installations. (A.L.B.)

  19. Contribution to the improvement of the evaluation methods of nuclear heating in reactors by using the Monte Carlo code TRIPOLI-4

    International Nuclear Information System (INIS)

    Peron, Arthur

    2014-01-01

    Technological irradiation programs carried out in experimental reactors are crucial for the support of the current nuclear fleet in terms of study and anticipation of the behavior under irradiation of fuels and structural materials. These programs make it possible to improve the safety of the current reactors and also to study materials for the new concepts of reactors. Irradiation conditions of materials in experimental reactors must be representative of those of nuclear power plants (NPPs). One of the main advantages of material testing reactors (MTRs) is to be able to carry out instrumented irradiations by adjusting experimental parameters, in particular the neutron flux and the temperature. The control of the parameter temperature of a device irradiated in an experimental reactor requires the knowledge of the nuclear heating (source term) due to the deposition of energy of the photons and the neutrons interacting in the device. A relevant evaluation of this heating is a key data for the thermal studies of design and safety of devices. The objective of this thesis is to improve the methods of the evaluation of nuclear heating in reactors. This work consists of the development of an innovating and complete coupled neutron-photon calculation scheme (allowing to obtain the contribution of neutrons, prompt gamma and decay gamma), mainly based on the 3D, continuous energy TRIPOLI-4 Monte Carlo transport code. An experimental validation of the calculation scheme has been performed, based on calorimetry measurements carried out in the OSIRIS reactor at CEA Saclay. Sensitivity studies have been undertaken to establish the impact of various parameters on nuclear heating calculations (in particular nuclear data) and to fix the final calculation scheme to be closer to the technological irradiation aspects. The thesis work leads to an operational and predictive tool for the nuclear heating estimation, meeting the experimentation needs of research reactors and can be

  20. Annual report of the Association EURATOM-Cea 2004 (executive summary)

    International Nuclear Information System (INIS)

    2004-01-01

    Progress in fusion technology is constant over the years and this report once again highlights a number of important steps that have been accomplished in this domain. This document is the executive summary of the full annual report, summarizing activities performed by the EURATOM-Cea association. This report has been organized into 10 issues: 1) physics integration, 2) reactor vessel, 3) plasma facing components, 4) remote handling, 5) magnets structures, 6) tritium breeding blankets, 7) structural material, 8) safety and environment, 9) system study, and 10) ITER site preparation

  1. Status of CEA studies on desalination on July 1, 1967

    International Nuclear Information System (INIS)

    Huyghe, J.; Vignet, P.; Courvoisier, P.; Frejacques, M.; Coriou, M.; Agostini, M.; Lackme, C.; CORPEL, M.; Thiriet, L.

    1967-01-01

    This publication contains a set of articles reporting studies on desalination performed within the CEA: preliminary draft of a desalination plant coupled with a nuclear reactor; the reverse osmosis; corrosion problems in seawater desalination plants; optimisation program of a distillation-based seawater desalination plant; activities of the department of analysis and applied chemistry in the field of desalination; abstract of a lecture on studies on price functions; studies of the department of steady isotopes on the formation of tartar depositions and their prevention; studies performed within the thermal transfer department

  2. Annual report of the Association EURATOM-Cea 2005 (executive summary)

    International Nuclear Information System (INIS)

    2005-01-01

    Progress in fusion technology is constant over the years and this report once again highlights a number of important steps that have been accomplished in this domain. This document is the executive summary of the full annual report, summarizing activities performed by the EURATOM-Cea association. This report has been organized into 10 issues: 1) physics integration, 2) reactor vessel, 3) plasma facing components, 4) remote handling, 5) magnets structures, 6) tritium breeding blankets, 7) structural material, 8) safety and environment, 9) system study, and 10) ITER site preparation

  3. CEA financial report 2007; CEA rapport financier 2007

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    This document provides financial data on the CEA for the year 2007. The management report (budget, resources, expenditures) and the accounting are detailed. The main management events of the year 2007 are presented. (A.L.B.)

  4. Decommissioning of the nuclear licensed facilities at the Fontenay aux Roses CEA center

    International Nuclear Information System (INIS)

    Jeanjacques, Michel; Piketty, Laurence; Letuhaire, Nathalie; Mandard, Lionel; Meden, Igor; Estivie, David; Boissonneau, Jean Francois; Fouquereau, Alain; Pichereau, Eric; Binet, Cedric

    2007-01-01

    Available in abstract form only. Full text of publication follows: The French Atomic Energy Commission (CEA) center at Fontenay aux Roses (CEN-FAR) is the Commission's oldest center is located in the southern suburbs of Paris. It was opened on 26 March 1946 to host the first French nuclear reactor ZOE that went critical on 12 December 1946. The first laboratories were installed in existing buildings on the site. (authors)

  5. The experimental reactor Osiris and the nuclear fuel technology for the P.W.R. reactors

    International Nuclear Information System (INIS)

    Lestiboudois, G.; Contenson, G. de; Genthon, J.P.; Molvault, M.; Roche, M.

    1977-01-01

    The possibility of employing research reactors to study and to improve the nuclear fuel of the power reactors is presented. Measurements of temperature, pressure, stresses, thermal balance, gamma spectrometry and neutron radiography, allow the study of fuel densification, the influence of the initial filling pressure on the fission gas release and the gadolinium efficiency evolution. The solutions of the problems of failed element detection, power increase, remote handling, are presented [fr

  6. Applications: fission, nuclear reactors. Fission: the various ways for reactors and cycles

    International Nuclear Information System (INIS)

    Bacher, P.

    1997-01-01

    A historical review is presented concerning the various nuclear reactor systems developed in France by the CEA: the UNGG (graphite-gas) system with higher CO 2 pressures, bigger fuel assemblies and powers higher than 500 MW e, allowed by studies on reactor physics, cladding material developments and reactor optimization; the fast neutron reactor system, following the graphite-gas development, led to the Superphenix reactor and important progress in simulation based on experiment and return of experience; and the PWR system, based on the american license, which has been successfully accommodated to the french industry and generates up to 75% of the electric power in France

  7. Study relating to the physico-chemical behaviour of heavy water in nuclear reactors

    International Nuclear Information System (INIS)

    Chenouard, J.; Dirian, G.; Roth, E.; Vignet, P.; Platzer, R.

    1959-01-01

    Chemical and isotope pollution, and radiolytic decomposition are the two most important ways in which heavy water becomes degraded in nuclear reactors. Chemical pollution has led to the creation of ion exchange purification loops specially designed for reactors: the report contains a description in detail of the application of this purification method in CEA research reactors, including the analysis required, results obtained, and their interpretation. The intelligence obtained on radiolytic decomposition with the same facilities is also discussed, as well as the recombination apparatus and control equipment utilized. Finally, investigation to date in the CEA on recombination circuits for power reactors is also discussed. (author) [fr

  8. CEA - 2014 risk management assessment

    International Nuclear Information System (INIS)

    Bonnevie, Edwige; Verwaerde, Daniel; Maillot, Bernard

    2015-06-01

    After introducing presentations of CEA managers in charge of risk management and controls, this document presents and comments the actions undertaken by the CEA and the obtained results in terms of risk management in different fields: protection and control of the environment, installation safety, health, safety and radiation protection, transport of hazardous materials, waste management, protection of sites, installations and heritage, management of emergency situations, management of legal risks, internal audits and controls. Other topics are addressed like the presentation of the risk management department, and the role of the CEA in the relationship between research and industry

  9. Annual report of the Association EURATOM-Cea 2005 (full report)

    International Nuclear Information System (INIS)

    Salmon, Th.; Le Vagueres, F.

    2005-01-01

    This annual report summarizes activities performed by the EURATOM-Cea association in 2005. The activities carried out in the field 'physics integration' are mainly linked to the ion cyclotron range of frequency antenna development and to the development of diagnostic components. The vacuum vessel studies have mainly focused at welding techniques and at qualification of inspection methods along the vacuum vessel inter-sector weld. On the plasma facing component side investigations have been performed on material knowledge (CuCrZr creep-fatigue studies, neutron effects on material properties of CFC, development and optimisation of Be/CuCrZr joining techniques and studies dedicated to the divertor. In the field 'magnets', EURATOM-Cea association has devoted a major part of its effort to the studies of advanced Nb 3 Sn strands for the toroidal field coil, and the first full size conductor sample was manufactured. Within the frame of Test Blanket Module (TBM), activities mainly concerned the improvement and completion of the TBM engineering design. Within the frame of the Helium Cooled Pebble Bed concept programmes, studies about the development of Li 2 TiO 3 pebbles are on going. The main objective of 2005 which was to improve the shape of Li 2 TiO 3 pebbles has been successfully achieved. EURATOM-Cea maintained significant involvement in the development of structural materials for a fusion reactor. A strong effort has been made on a program of laser detritiation associated with remote handling. (A.C.)

  10. Bivalent fragment of the ior-CEA1 antibody. A challenge to the positive CEA tumors radioimmunotherapy

    International Nuclear Information System (INIS)

    Ravelo, Rolando; Sanchez, Iradia; Pimentel, Gilmara; Oliva, Juan; Perez, Lincidio; Ayala, Marta; Bell, Hansell; Gavilondo, Jorge

    2006-01-01

    The directed radiotherapy of the solid tumors with fragments recombinants of radiolabelled antibodies is a topic of current investigation, so much at preclinical level as clinical. This work describes the preclinical characterization of a new fragment type diabody of the AcMo ior CEA1 that has been labelled with 131 I for their use in the diagnosis and the therapy of CEA positive tumors. The radiolabelling methodology used allows the incorporation of more than 90% of the radio iodine to the molecule without committing the capacity of recognition of its antigen significantly. The combination of the favourable properties pharmacy kinetic and high selective accumulation in the tumor, they make of the diabody anti CEA an appropriate candidate for the radioimmunodiagnosis and the radioimmunotherapy of tumors that expresses CEA (Author)

  11. CEA - Assessment of risk management 2013

    International Nuclear Information System (INIS)

    Bigot, Bernard; Bonnevie, Edwige; Maillot, Bernard

    2014-06-01

    After some introducing texts by CEA managers, this report proposes a rather detailed overview and presentation of CEA activities, objectives and obtained results in different fields: protection and control of the environment, installation safety, health, safety and radiation protection, transports of hazardous materials, waste management, protection of sites, installations and heritage, management of emergency situations, management of legal risks, internal controls and audits, activity of the risk management department, CEA activities from research to industry

  12. Actinide neutron induced cross section measurements using the oscillation technique in the Minerve reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bernard, B.; Leconte, P.; Gruel, A.; Antony, M.; Di-Salvo, J.; Hudelot, J.P.; Pepino, A.; Lecluze, A. [CEA Cadarache, DEN/CAD/DER/SPRC/LEPh, 13 - Saint-Paul-lez-Durance (France)

    2009-07-01

    CEA is deeply involved research programs concerning nuclear fuel advanced studies (actinides, plutonium), waste management, the scientific and technical support of French PWR reactors and EPR reactor, and innovative systems. In this framework, specific neutron integral experiments have been carried out in the critical ZPR (zero power reactor) facilities of the CEA at Cadarache such as MINERVE, EOLE and MASURCA. This paper deals with MINERVE Pool Reactor experiments. MINERVE is mainly devoted to neutronics studies of different reactor core types. The aim is to improve the knowledge of the integral absorption cross sections of actinides (OSMOSE program), of new absorbers (OCEAN program) and also for fission Products (CBU program) in thermal, epithermal and fast neutron spectra. (authors)

  13. Combined analysis of neutron and photon flux measurements for the Jules Horowitz reactor core mapping

    Energy Technology Data Exchange (ETDEWEB)

    Fourmentel, D.; Villard, J. F.; Lyoussi, A. [DEN Reactor Studies Dept., French Nuclear Energy and Alternative Energies Commission, CEA Cadarache, 13108 Saint Paul-Lez-Durance (France); Reynard-Carette, C. [Laboratoire Chimie Provence LCP UMR 6264, Univ. of Provence, Centre St. Jerome, 13397 Marseille Cedex 20 (France); Bignan, G.; Chauvin, J. P.; Gonnier, C.; Guimbal, P.; Malo, J. Y. [DEN Reactor Studies Dept., French Nuclear Energy and Alternative Energies Commission, CEA Cadarache, 13108 Saint Paul-Lez-Durance (France); Carette, M.; Janulyte, A.; Merroun, O.; Brun, J.; Zerega, Y.; Andre, J. [Laboratoire Chimie Provence LCP UMR 6264, Univ. of Provence, Centre St. Jerome, 13397 Marseille Cedex 20 (France)

    2011-07-01

    We study the combined analysis of nuclear measurements to improve the knowledge of the irradiation conditions in the experimental locations of the future Jules Horowitz Reactor (JHR). The goal of the present work is to measure more accurately neutron flux, photon flux and nuclear heating in the reactor. In a Material Testing Reactor (MTR), nuclear heating is a crucial parameter to design the experimental devices to be irradiated in harsh nuclear conditions. This parameter drives the temperature of the devices and of the samples. The numerical codes can predict this parameter but in-situ measurements are necessary to reach the expected accuracy. For this reason, one objective of the IN-CORE program [1] is to study the combined measurements of neutron and photon flux and their cross advanced interpretation. It should be reminded that both neutron and photon sensors are not totally selective as their signals are due to neutron and photon interactions. We intend to measure the neutron flux by three different kinds of sensors (Uranium Fission chamber, Plutonium Fission chamber and Self Powered Neutron Detector), the photon flux by two different sensors (Ionization chamber and Self Powered Gamma Detector) and the nuclear heating by two different ones (Differential calorimeter and Gamma Thermometer). For the same parameter, we expect that the use of different kinds of sensors will allow a better estimation of the aimed parameter by mixing different spectrum responses and different neutron and gamma contributions. An experimental test called CARMEN-1 is scheduled in OSIRIS reactor (CEA Saclay - France) at the end of 2011, with the goal to map irradiation locations in the reactor reflector to get a first validation of the analysis model. This article focuses on the sensor selection for CARMEN-1 experiment and to the way to link neutron and photon flux measurements in view to reduce their uncertainties but also to better assess the neutron and photon contributions to nuclear

  14. Combined analysis of neutron and photon flux measurements for the Jules Horowitz reactor core mapping

    International Nuclear Information System (INIS)

    Fourmentel, D.; Villard, J. F.; Lyoussi, A.; Reynard-Carette, C.; Bignan, G.; Chauvin, J. P.; Gonnier, C.; Guimbal, P.; Malo, J. Y.; Carette, M.; Janulyte, A.; Merroun, O.; Brun, J.; Zerega, Y.; Andre, J.

    2011-01-01

    We study the combined analysis of nuclear measurements to improve the knowledge of the irradiation conditions in the experimental locations of the future Jules Horowitz Reactor (JHR). The goal of the present work is to measure more accurately neutron flux, photon flux and nuclear heating in the reactor. In a Material Testing Reactor (MTR), nuclear heating is a crucial parameter to design the experimental devices to be irradiated in harsh nuclear conditions. This parameter drives the temperature of the devices and of the samples. The numerical codes can predict this parameter but in-situ measurements are necessary to reach the expected accuracy. For this reason, one objective of the IN-CORE program [1] is to study the combined measurements of neutron and photon flux and their cross advanced interpretation. It should be reminded that both neutron and photon sensors are not totally selective as their signals are due to neutron and photon interactions. We intend to measure the neutron flux by three different kinds of sensors (Uranium Fission chamber, Plutonium Fission chamber and Self Powered Neutron Detector), the photon flux by two different sensors (Ionization chamber and Self Powered Gamma Detector) and the nuclear heating by two different ones (Differential calorimeter and Gamma Thermometer). For the same parameter, we expect that the use of different kinds of sensors will allow a better estimation of the aimed parameter by mixing different spectrum responses and different neutron and gamma contributions. An experimental test called CARMEN-1 is scheduled in OSIRIS reactor (CEA Saclay - France) at the end of 2011, with the goal to map irradiation locations in the reactor reflector to get a first validation of the analysis model. This article focuses on the sensor selection for CARMEN-1 experiment and to the way to link neutron and photon flux measurements in view to reduce their uncertainties but also to better assess the neutron and photon contributions to nuclear

  15. Emission-line maps with OSIRIS-TF: The case of M101

    Science.gov (United States)

    Méndez-Abreu, J.

    2013-05-01

    We investigate the suitability of GTC/OSIRIS Tunable Filters (TFs) for obtaining emission-line maps of extended objects. We developed a technique to reconstruct an emission-line image from a set of images taken at consecutive central wavelengths. We demonstrate the feasibility of the reconstruction method by generating a flux calibrated Hα image of the well-known spiral galaxy M101. We tested our emission-line fluxes and ratios by using data present in the literature. We found that the differences in both Hα fluxes and N II/Hα line ratios are ~15% and ~50%, respectively. These results are fully in agreement with the expected values for our observational setup. The proposed methodology will allow us to use OSIRIS/GTC to perform accurate spectrophotometric studies of extended galaxies in the local Universe.

  16. Memoirs of a Cea veteran

    Energy Technology Data Exchange (ETDEWEB)

    Puill, A

    2001-07-01

    A brief account is given of the way in which nuclear energy has developed in France and elsewhere over the last fifty years: options developed by the French Atomic Energy Commission (CEA), naval propulsion, development of pressurised water reactors, MOX and thorium fuels. Afterwards, the prospectives for the 21. century will be discussed. Considering that natural resources are depleting while releases of both greenhouse gases and world population are increasing, an active energy policy will have to be implemented with due consideration for social equity and solidarity. It is in this context that the developed countries will have to give preference, beyond savings, to renewable sources of energy, including of course, nuclear energy. Nuclear energy can continue to develop in the long term, provided fast breeder technology is developed at some point. As far as transport is concerned, hydrogen technology, which is clean and renewable, is promising, provided it is generated by nuclear energy. (author)

  17. Memoirs of a Cea veteran

    International Nuclear Information System (INIS)

    Puill, A.

    2001-01-01

    A brief account is given of the way in which nuclear energy has developed in France and elsewhere over the last fifty years: options developed by the French Atomic Energy Commission (CEA), naval propulsion, development of pressurised water reactors, MOX and thorium fuels. Afterwards, the prospectives for the 21. century will be discussed. Considering that natural resources are depleting while releases of both greenhouse gases and world population are increasing, an active energy policy will have to be implemented with due consideration for social equity and solidarity. It is in this context that the developed countries will have to give preference, beyond savings, to renewable sources of energy, including of course, nuclear energy. Nuclear energy can continue to develop in the long term, provided fast breeder technology is developed at some point. As far as transport is concerned, hydrogen technology, which is clean and renewable, is promising, provided it is generated by nuclear energy. (author)

  18. Thermal neutron capture cross section for the K isomer 177Lum

    International Nuclear Information System (INIS)

    Belier, G.; Roig, O.; Daugas, J.-M.; Giarmana, O.; Meot, V.; Letourneau, A.; Marie, F.; Foucher, Y.; Aupiais, J.; Abt, D.; Jutier, Ch.; Le Petit, G.; Bettoni, C.; Gaudry, A.; Veyssiere, Ch.; Barat, E.; Dautremer, T.; Trama, J.-Ch.

    2006-01-01

    The thermal neutron radiative capture cross section for the K isomeric state in 177 Lu has been measured for the first time. Several 177 Lu m targets have been prepared and irradiated in various neutron fluxes at the Lauee Langevin Institute in Grenoble and at the CEA reactors OSIRIS and ORPHEE in Saclay. The method consists of measuring the 178 Lu activity by γ-ray spectroscopy. The values obtained in four different neutron spectra have been used to calculate the resonance integral of the radiative capture cross section for 177 Lu m . In addition, an indirect method leads to the determination of the 177 Lu g neutron radiative capture cross section

  19. A review of the current thermal-hydraulic modeling of the Jules Horowitz Reactor: A loss of flow accident analysis

    International Nuclear Information System (INIS)

    Pegonen, R.; Bourdon, S.; Gonnier, C.; Anglart, H.

    2014-01-01

    Highlights: • CEA methodology for thermal-hydraulic calculations in the JHR reactor is described. • Thermal-hydraulics of the JHR is analyzed during LOFA using CATHARE and FLICA4. • Safety criteria, important modeling parameters and correlations are presented. • Possible improvements of the current methodology are discussed and proposed. - Abstract: The newest European high performance material testing reactor, the Jules Horowitz Reactor, will support existing and future nuclear reactor designs. The reactor is under construction at CEA Cadarache research center in France and is expected to start operation at the end of this decade. R and D and analytical works have already been performed to set-up the methodology for thermal-hydraulic calculations of the reactor. This paper presents the off-line coupled thermal-hydraulic modeling of the reactor using the CATHARE system code and the FLICA4 core analysis code. The main objective of the present work is to analyze the thermal-hydraulic calculations of the reactor during the loss of flow accident using CEA methodology. Possible improvements of the current methodology are shortly discussed and suggested

  20. Saclay - 50 years / CEA 1945-95

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    Central in the infrastructure through which France obtains some 80% of its electric power from nuclear energy stands the French Atomic Energy Authority (Commissariat à l'Energie Atomique - CEA). This year the CEA celebrates its Golden Jubilee. Mastery of nuclear energy goes hand-in-hand with fundamental research in the fields of nuclear and sub-nuclear physics, and the founders of the CEA, like F. Joliot and F. Perrin, considered it essential to relaunch fundamental research in France after the Second World War. In particular, A. Messiah's courses on quantum mechanics made a considerable contribution to the re-establishment of a French school of atomic and sub-atomic physics. As the CEA expanded and nuclear industry grew up, the need was shown for close links between fundamental research and its applications. In addition, the CEA realized how important it was to become a part of the national and international scientific community as highly effective cooperation was developing. The CEA has drawn a wealth of scientific, cultural and intellectual benefits from its collaboration with CERN. During the same period, as fundamental particle physics research has been making spectacular progress, its requirements have grown commensurately. It is not therefore surprising that CERN needs partners capable of bringing together the domains of fundamental research and major equipment and of promoting a dialogue between research and industry. As was pointed out by Jacques Haissinski, head of the Department of Astrophysics, Particle Physics, Nuclear Physics and Associated Instruments (DAPNIA), the CEA, set up to develop major programmes for applying nuclear processes, is particularly well equipped to design, build and operate the huge instruments for exploring the infinitely small and the infinitely large. Tomorrow's nuclear industry needs and will continue to need fundamental research, with its openness and its cooperation. Particle physics needs and will continue

  1. Osiris and SOMBRERO inertial fusion power plant designs - summary, conclusions, and recommendations

    International Nuclear Information System (INIS)

    Meier, Wayne R.

    1994-01-01

    An 18 month study to evaluate the potential of inertial fusion energy (IFE) for electric power production has been completed. The primary objective of the study was to provide the US Department of Energy with an evaluation of the potential of inertial fusion for electric power production. The study included the conceptual design of two inertial fusion power plants. Osiris uses an induction linac heavy ion beam driver, and SOMBRERO uses a krypton fluoride laser driver. Conceptual designs were completed for the reactors, power conversion and plant facilities, and drivers. Environmental and safety aspects, technical issues, technology development needs, and economics of the final point designs were assessed and compared. This paper summarizes the results and conclusions of the conceptual designs and results of the assessment studies. We conclude that IFE has the potential of producing technically credible designs with environmental, safety, and economics characteristics that are just as attractive as magnetic fusion. Realizing this potential will require additional research and development on target physics, chamber design, target production and injection systems, and drivers. ((orig.))

  2. INIS, CEA and nuclear terminology; INIS, CEA et terminologie nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Surmont, J.; Brulet, C.; Constant, A.; Guille, N.; Le Blanc, A.; Mouffron, O.; Anguise, P.; Jouve, J.J

    2007-07-01

    This poster, prepared for the fifth edition of the meetings of scientific and technical information professionals (RPIST, Nancy (France)), presents, first, the INIS information system, its content and coverage, the French participation to this system and the role of the CEA-Saclay as France's official representative for this system. Then it presents the INIS thesaurus with its different levels as a terminological tool for the indexing of documents and for searching documents inside the database. Finally, the very first electronic version of the multilingual thesaurus is introduced. Several national INIS centres, including the CEA-Saclay, have contributed to the translation of lists of new terms and of forbidden terms (synonyms). (J.S.)

  3. The CEA at the heart of great new challenges - Annual report 2015. The CEA - Financial report 2015

    International Nuclear Information System (INIS)

    2016-06-01

    The French Alternative Energies and Atomic Energy Commission (CEA) is a key player in research, development and innovation in four main areas: defence and security, nuclear energy (fission and fusion), technological research for industry, fundamental research in the physical sciences and life sciences. Drawing on its widely acknowledged expertise, the CEA actively participates in collaborative projects with a large number of academic and industrial partners. The CEA is established in nine centers spread throughout France. It works in partnership with many other research bodies, local authorities and universities. Within this context, the CEA is a stakeholder in a series of national alliances set up to coordinate French research in energy (ANCRE), life sciences and health (AVIESAN), digital science and technology (ALLISTENE), environmental sciences (AllEnvi) and human and social sciences (ATHENA). The CEA in figures (2015): 9 research centres; 15958 technicians, engineers, researchers and staff; 51 joint research units (UMR); 53 framework agreements with universities and schools; 753 priority patents filed in 2015; 27 Equipex (facilities of excellence); 33 Labex (Laboratories of excellence); 3 Idex (Initiatives of excellence); 187 start-ups since 1972 in the innovative technologies sector; 4,1 billion euros budget; 438 ongoing European projects in 2015. This document is the activity report of CEA over the year 2015 (Defence, energy, technologies, fundamental research..). It is followed by a Management and a financial report (annual Financial Statements)

  4. Information technology in the strategy of digestive surgery. (2) Advances of CAD system using OsiriX

    International Nuclear Information System (INIS)

    Sugimoto, Maki; Yasuda, Hideki; Koda, Keiji; Yamazaki, Masato; Tezuka, Tohru; Kosugi, Chihiro; Watayo, Yoshihisa; Naka, Shuji

    2007-01-01

    OsiriX, one of information technology (IT) product in medicine, is an image processing system developed by surgeons and its software for Mac OS can be installed free of charge (http://homepage.mac.com/rossetantoine/osrix/). The present review describes the practical application of this computer-aided diagnostic (CAD) tool mainly in the field of surgery of hepato-biliary-pancreatic system. Authors are successfully utilizing the OsiriX for pre-operative diagnosis by modalities of multidetector-row CT (MDCT), MRI and PET images, for simulation of surgery by volume rendering, carbon dioxide MDCT cholangiopancreatography (CMCP), 3D vascular construction MDCT angiography and virtual reality, and for navigation during the actual operation. The machine they use is 16-row MDCT LightSpeed Ultra 16 (GE Healthcare), and their data are processed through the Digital Imaging and Communications in Medicine (DICOM) viewer OsiriX 2.6, Power Mac G5, MacBook Pro (Apple Computer, Inc.) and 3D image processing engine (TeraRecon, Inc.). Presented are details of decision of region of interest (ROI), 3D ROI extraction by region-growing, MacBook Pro and iPod, and IT surgery by OsiriX, which are still being improved day by day. (T.I.)

  5. CEA - 2012 Annual Report, 2012 Financial Statements

    International Nuclear Information System (INIS)

    2013-01-01

    In its first part, this report proposes an overview of activities within the CEA. They concern the CEA's programs on low on carbon energies and associated fundamental researches, on defence and global security and associated fundamental researches, on information technologies and associated fundamental researches, on health technologies and associated fundamental researches, and on very large research infrastructures and associated fundamental researches. The second part addresses the scientific assessment, activities related to teaching and training, to innovation towards enterprises, and to support to valorization. It also indicates prices awarded to the CEA. The third part addresses CEA management and institutional relationships, human resources, international relationships, activities related to communication and information diffusion, and risk management. The fourth part describes the CEA organization, its governance and its various bodies. The second volume contains the financial statements for 2012

  6. Immersed multiple device for the control of the irradiated PWR fuel pins in the reloadable loop in the OSIRIS pond

    International Nuclear Information System (INIS)

    Farny, G.

    1983-01-01

    With respect to the dynamics of the degradation of the PWR fuel in transient, normal and abnormal regions, a new multi-device immersed in the cooling pond of the OSIRIS reactor, is studied. The multiple device is subjected to three examinations: (1) visual studying and video-recording of the appearance of the fuel pins, (2) metrology of the pins, (3) investigation of the induced Foucault currents in the fuel cans. Attention is chiefly paid to the last point; the other ones - being closely related - are only touched on whenever needed. It is concluded that quality control of the fuel pins is possible by means of Foucault currents without applying mechanical constraints and without interfering with the cooling rate. (Auth.)

  7. Characterization of gastric adenocarcinoma cell lines established from CEA424/SV40 T antigen-transgenic mice with or without a human CEA transgene

    International Nuclear Information System (INIS)

    Nöckel, Jessica; Engel, Natasja K van den; Winter, Hauke; Hatz, Rudolf A; Zimmermann, Wolfgang; Kammerer, Robert

    2006-01-01

    Gastric carcinoma is one of the most frequent cancers worldwide. Patients with gastric cancer at an advanced disease stage have a poor prognosis, due to the limited efficacy of available therapies. Therefore, the development of new therapies, like immunotherapy for the treatment of gastric cancer is of utmost importance. Since the usability of existing preclinical models for the evaluation of immunotherapies for gastric adenocarcinomas is limited, the goal of the present study was to establish murine in vivo models which allow the stepwise improvement of immunotherapies for gastric cancer. Since no murine gastric adenocarcinoma cell lines are available we established four cell lines (424GC, mGC3, mGC5, mGC8) from spontaneously developing tumors of CEA424/SV40 T antigen (CEA424/Tag) mice and three cell lines derived from double-transgenic offsprings of CEA424/Tag mice mated with human carcinoembryonic antigen (CEA)-transgenic (CEA424/Tag-CEA) mice (mGC2 CEA , mGC4 CEA , mGC11 CEA ). CEA424/Tag is a transgenic C57BL/6 mouse strain harboring the Tag under the control of a -424/-8 bp CEA gene promoter which leads to the development of invasive adenocarcinoma in the glandular stomach. Tumor cell lines established from CEA424/Tag-CEA mice express the well defined tumor antigen CEA under the control of its natural regulatory elements. The epithelial origin of the tumor cells was proven by morphological criteria including the presence of mucin within the cells and the expression of the cell adhesion molecules EpCAM and CEACAM1. All cell lines consistently express the transgenes CEA and/or Tag and MHC class I molecules leading to their susceptibility to lysis by Tag-specific CTL in vitro. Despite the presentation of CTL-epitopes derived from the transgene products the tumor cell lines were tumorigenic when grafted into C57BL/6, CEA424/Tag or CEA424/Tag-CEA-transgenic hosts and no significant differences in tumor take and tumor growth were observed in the different hosts

  8. OCAMS: The OSIRIS-REx Camera Suite

    Science.gov (United States)

    Rizk, B.; Drouet d'Aubigny, C.; Golish, D.; Fellows, C.; Merrill, C.; Smith, P.; Walker, M. S.; Hendershot, J. E.; Hancock, J.; Bailey, S. H.; DellaGiustina, D. N.; Lauretta, D. S.; Tanner, R.; Williams, M.; Harshman, K.; Fitzgibbon, M.; Verts, W.; Chen, J.; Connors, T.; Hamara, D.; Dowd, A.; Lowman, A.; Dubin, M.; Burt, R.; Whiteley, M.; Watson, M.; McMahon, T.; Ward, M.; Booher, D.; Read, M.; Williams, B.; Hunten, M.; Little, E.; Saltzman, T.; Alfred, D.; O'Dougherty, S.; Walthall, M.; Kenagy, K.; Peterson, S.; Crowther, B.; Perry, M. L.; See, C.; Selznick, S.; Sauve, C.; Beiser, M.; Black, W.; Pfisterer, R. N.; Lancaster, A.; Oliver, S.; Oquest, C.; Crowley, D.; Morgan, C.; Castle, C.; Dominguez, R.; Sullivan, M.

    2018-02-01

    The OSIRIS-REx Camera Suite (OCAMS) will acquire images essential to collecting a sample from the surface of Bennu. During proximity operations, these images will document the presence of satellites and plumes, record spin state, enable an accurate model of the asteroid's shape, and identify any surface hazards. They will confirm the presence of sampleable regolith on the surface, observe the sampling event itself, and image the sample head in order to verify its readiness to be stowed. They will document Bennu's history as an example of early solar system material, as a microgravity body with a planetesimal size-scale, and as a carbonaceous object. OCAMS is fitted with three cameras. The MapCam will record color images of Bennu as a point source on approach to the asteroid in order to connect Bennu's ground-based point-source observational record to later higher-resolution surface spectral imaging. The SamCam will document the sample site before, during, and after it is disturbed by the sample mechanism. The PolyCam, using its focus mechanism, will observe the sample site at sub-centimeter resolutions, revealing surface texture and morphology. While their imaging requirements divide naturally between the three cameras, they preserve a strong degree of functional overlap. OCAMS and the other spacecraft instruments will allow the OSIRIS-REx mission to collect a sample from a microgravity body on the same visit during which it was first optically acquired from long range, a useful capability as humanity reaches out to explore near-Earth, Main-Belt and Jupiter Trojan asteroids.

  9. CEA 2009 annual report; CEA rapport annuel 2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-07-01

    After an indication of several key figures about the activity of the CEA (Centre d'Etudes Atomiques) and its relationship with the academic as well as the industrial field, in France and worldwide, this 2009 annual report presents its various research programs in the field of defence and of global security: basic research (nuclear weapons and propulsion, struggle against proliferation and terrorism) and applied research (nuclear deterrence, national and international security). Then, it presents the programs in the field of de-carbonated energy: basic research (in material science and in life sciences) and applied research (fission energy, fusion energy, new energy technologies). A last group of research programs deals with information and health technologies and concerns life and material sciences, micro- and nano-technologies, software technologies. Interaction with other research institutions and bodies is also evoked. A brief scientific assessment is proposed. Finally, the different structures building the CEA are presented

  10. R and D on early detection of the Total Instantaneous Blockage for 4. Generation Reactors - Inventory of non-nuclear methods investigated by the CEA

    International Nuclear Information System (INIS)

    Paumel, K.; Jeannot, J.-P.; Vanderhaegen, M.; Massacret, N.; Jeanne, T.; Laffont, G.

    2013-06-01

    In the safety analysis for the core of the 4. Generation Reactors, the Total Instantaneous Blockage (TIB) is a hypothetic accident scenario involving the melting of the blocked subassembly with a risk of propagation to the neighbouring subassemblies. To avoid this latter consequence a detection system has to scram the reactor. For Superphenix or EFR project a Delayed Neutron Detection Integrated (DND I) was considered as efficient to limit the melting to the first neighbouring subassemblies. Nonetheless for the CFV core the objective of improving the safety leads to limit the melting to the blocked subassembly. For this purpose, the CEA has launched a program development to find a new detection method. This paper provides a brief review of the feedback of R and D, progress and program on the various early non-nuclear detection methods investigated by the CEA: - Temperature measurement at the subassemblies outlet by thermocouples. The advantage of this method is that it will require no additional instrumentation to that already present for continuous monitoring. - Temperature measurement at the subassemblies outlet by Optical Fibers Bragg Grating (OFBG). This technology has the electromagnetic immunity, compactness and short response time. - Temperature measurement at the subassemblies outlet by ultrasound. The measuring point is located closer to the head subassembly and the response time could be shorter. - Acoustic detection of sodium boiling. Boiling occurs early in the accident progress and the area to be monitored may be covered by few sensors. - Subassemblies loss of flow detection by eddy-current flowmeters. This method seems logically the easiest and the most immediate method to detect a blockage. To date, none of these methods has been fully demonstrated to be feasible. It should be noted that temperature measurement methods will probably consist of the detection of a low increase rate using specific signal processing. These methods have been compared

  11. The launching of the construction of the Jules Horowitz Reactor

    International Nuclear Information System (INIS)

    Anon.

    2007-01-01

    In March 2007 the French deputy minister of industry has officially launched the construction of the new research reactor called Jules Horowitz (RJH) on the Cea site of Cadarache. RJH, that is due to operate in 2014, will be used to study the aging process of irradiated materials in any type of reactors, the behaviour of new nuclear fuels irradiated in different configurations and scenarios, and to produce radionuclides for nuclear medicine and high-quality doped silicon for the electronics industry. The investment that reaches 500 million euros is dispatched between Cea (50%), EDF (20%), Areva (10%) and foreign contributors (20%). (A.C.)

  12. Progress report of the French program, and basic design of the Jules Horowitz reactor

    International Nuclear Information System (INIS)

    Ballagny, A.

    1998-01-01

    Since the SILOE reactor was shutdown on December 23, 1997, France has been entirely depending on the OSIRIS reactor to conduct the material and fuel irradiation programmes necessary to the evolution of its nuclear power plants and to prepare the future by analysing further reactor designs which might originate in other strategies, namely in the fuel cycle field. The Jules Horowitz reactor, which operation scheduled to start in 2006, will last 50 years, must cover all irradiation needs including, as far as possible, those related to fast breeder reactor studies, more particularly since the SUPERPHENIX reactor shutdown was announced. RJH reactor studies therefore focus on the increase of flux levels and the search for the limit performance of U 3 Si 2 based MTR fuels. (author)

  13. CEA monitoring of palliative treatment for colorectal carcinoma.

    Science.gov (United States)

    Herrera, M A; Chu, T M; Holyoke, E D; Mittelman, A

    1977-01-01

    Palliative treatment was applied to 131 cases of unresectable or palliatively resected colorectal carcinoma being monitored with serial CEA determinations. There were 84 instances of disease progression with 67 (80%) of them showing an increase in CEA above pretreatment levels or maintaining high levels, and 17 (20%) showing a fall when compared to pretreatment values or maintaining low initial values. There was a clear-cut regression of the disease in only 9 instances. In all 9, the CEA clearly dropped or maintained low valles throughout the period of regression. No patient in regression had a rise or maintained an elevated CEA level. These changes in CEA followed closely the clinical response of our patient to the use of a particular agent, although for the Nitrosourea compounds there may be a tendency to lower the CEA regardless of the patient's tumor response to the drug. This could be due to the fact that the Nitrosoureas produce a diffuse block of cellular activity, both at the nucleous and cytoplasm; while other compounds act as alkylating agents or by inhibition of enzymes involved in the metabolism of nucleic acids (i.e., 5-FU inhibiting thymidylate synthetase). In general, longer survival was found in those patients who had initially lower levels of CEA as compared to those with high initial levels. The patients with a favorable CEA response to the treatment (falling CEA or maintained low value), even in many who did not show a clinical response had a longer survival than the group with rising or stable high levels. The main value in CEA monitoring of patients resides in its correlation with the amount of disease present and then its ability to detect progression of tumor mass which is not clinically measurable. PMID:64132

  14. Research on nuclear energy in the fields of fuel cycle, PWR reactors and LMFBR reactors

    International Nuclear Information System (INIS)

    Barre, B.; Camarcat, N.

    1995-01-01

    In this article we present the CEA research programs to improve the safety of the next generation of reactors, to manage the Plutonium and the wastes of the fuel cycle end and to ameliorate the competitiveness. 6 refs

  15. Demodicidosis en pacientes con rosácea

    Directory of Open Access Journals (Sweden)

    Edhizon Trejo Mucha

    2007-01-01

    Full Text Available Objetivo: Determinar la frecuencia de demodicidosis y sus características clínicas en pacientes con rosácea. Materiales y métodos: Estudio de casos y controles en 42 pacientes con rosácea y 42 controles para describir la presencia y densidad de D. folliculorum. El estudio se realizó en el Hospital Nacional Cayetano Heredia entre marzo y setiembre del 2004, utilizándose la técnica de Tello. Resultados: Demodex folliculorum fue encontrado en los 42 pacientes con rosácea (100% y en 13 (31,0% del grupo control, (p= 0,000. La exposición a gatos, la crianza de roedores y cerdos, la seborrea y el uso de corticoides tópicos fueron mas frecuentes en los pacientes con rosácea. Conclusiones: La presencia de Demodex folliculorum fue más frecuente en los pacientes con rosácea. (Rev Med Hered 2007;18:15-21.

  16. The dismantling of CEA nuclear installations

    International Nuclear Information System (INIS)

    Piketty, Laurence

    2016-03-01

    After having indicated locations of French nuclear installations which are currently being dismantled (about 30 installations), and recalled the different categories of radioactive wastes with respect to their activity level and the associated storage options, this article gives an overview of various aspects of dismantling, more precisely in the case of installations owned and managed by the CEA. These operations comprise the dismantling itself, the recovery and packaging of wastes, old effluents and spent fuels. The organisation and responsible departments within the CEA are presented, and the author outlines some operational problematic issues met due to the age of installations (traceability of activities, regulation evolutions). The issue of financing is then discussed, and its uncertainties are outlined. The dismantling strategy within the CEA-DEN is described, with reference to legal and regulatory frameworks. The next parts of the article address the organisation and the economic impact of these decontamination and dismantling activities within the CEA-DEN, highlight how R and D and advanced technology are a support to this activities as R and D actions address all scientific and technical fields of nuclear decontamination and dismantling. An overview of three important dismantling works is proposed: Fontenay-aux-Roses, the Marcoule CEA centre (a reference centre in the field of nuclear dismantling and decontamination) and the Grenoble CEA centre (reconversion in R and D activities in the fields of technologies of information, of communication, technologies, for health, and in renewable energies). The last part addresses the participation to the Strategic Committee of the Nuclear Sector (CSFN)

  17. Italian position paper on the safety analysis of liquid metal fast breeder reactors as related to sodium fires. The PEC reactor

    International Nuclear Information System (INIS)

    Gerosa, A.

    1983-01-01

    To obtain a deep understanding of physical phenomena and engineering problems connected to sodium fires, and to optimize the utilization of human and financial resources available, CNEN (now ENEA) has decided to join the French Commissariat a l'Energie Atomique (CEA) in the realization of a Franco-Italian experimental programme on sodium fires, named ESMERALDA. As for design preventions for PEC reactor (a fast flux, liquid metal cooled, fuel element testing reactor) fundamental choices were made taking into account all available knowledge, but with particular reference to the results of CEA's previous experiments on sodium fires. More detailed design analysis will be possible in the future, based on experimental results coming from the ESMERALDA programme

  18. CEA 2005 annual report

    International Nuclear Information System (INIS)

    2006-01-01

    This document is the 2005 activity report of the French atomic energy commission (CEA). The CEA is a main actor of nuclear research, development and innovation and is involved in three main domains: energy, defense/security, and information/health technologies thanks to high quality research works. With a manpower of 15000 researchers and collaborators with internationally acknowledged competences, the CEA is a driving force of industrial innovation and develops partnerships with French and European industries. It also warrants the perenniality of nuclear dissuasion. This report presents these different aspects of the CEA activities: 1 - defense-security: simulation program, opening to the scientific community, nuclear warheads, nuclear propulsion, cleansing of Rhone valley facilities, permanent monitoring of treaties respect, fight against terrorism; 2 - energy: optimization of the industrial park, advances in long lived radioactive wastes management, future nuclear systems, cleansing and dismantling integration, European nuclear energy research, new energy technologies; 3 - information and health technologies: major challenge of micro- and nano-technologies, key role of software technologies and complex systems; 4 - big research facilities opened to the scientific and industrial communities; 5 - scientific status: scientific evaluation process, prices and honors; 6 - programs support: revisited strategic control, confirmed simplification, active employment and training policy, teaching and training, technological valorization, international relations, communication, continuous quality approach, mastery of facilities safety, security, environmental control, a key-year for information systems. A financial report is attached to the document. (J.S.)

  19. 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)

  20. Thermal assessment of sunlight impinging on OSIRIS-REx OCAMS PolyCam, OTES, and IMU-sunshade MLI blankets in flight

    Science.gov (United States)

    Choi, Michael K.

    2017-09-01

    The NASA Origins, Spectral Interpretation, Resource Identification, Security, Regolith Explorer (OSIRIS-REx) spacecraft was successfully launched into orbit on September 8, 2016. It is traveling to a near-Earth asteroid (101955) Bennu, study it in detail, and bring back a pristine sample to Earth for scientific analyses. At the Outbound Cruise nominal spacecraft attitude, with Sun on +X, sunlight impinges on the OSIRIS-REx camera suite (OCAMS) PolyCam sunshade multilayer insulation (MLI) with microporous black polytetrafluoroethylene (PTFE), a portion of the PolyCam optics support tube (MLI with germanium black Kapton (GBK)), a portion of the OSIRIS-REx Thermal Emission Spectrometer (OTES) sunshade (MLI with GBK), the Inertia Measurement Unit (IMU) sunshade (MLI with GBK), and the OSIRIS-REx Laser Altimeter (OLA) sunshade (MLI with GBK). Sunlight is reflected or scattered by the above MLIs to the other components on the forward (+Z) deck. It illuminates the forward deck. A detailed thermal assessment on the solar impingement has been performed for the Proximity Ops at the asteroid, Touch-and-Go sample acquisition, and Return Cruise mission phases.

  1. Decontamination and dismantling at the CEA

    International Nuclear Information System (INIS)

    2006-01-01

    This document presents the dismantling policy at the CEA (French Research Center on the atomic energy), the financing of the decontamination and the dismantling, the regulatory framework, the knowledge and the technology developed at the CEA, the radiation protection, the environment monitoring and the installations. (A.L.B.)

  2. Progress in fusion reactors blanket analysis and evaluation at CEA

    International Nuclear Information System (INIS)

    Proust, E.; Gervaise, F.; Carre, F.; Chevereau, G.; Doutriaux, D.

    1986-09-01

    In the frame of the recent CEA studies aiming at the development, evaluation and comparison of solid breeder blanket concepts in view of their adaptation to NET, the evaluation of specific questions related to the first wall design, the present paper examines first the performances of a helium cooled toroidal blanket design for NET, based on innovative Beryllium/Ceramics breeder rod elements. Neutronic and thermo-mechanical optimisation converges on a concept featured by a breeding capability in excess of 1.2, a reasonnable pumping power of 1% and a narrow breeder temperature range (470+-30 deg C of the breeder), the latter being largely independent of the power level. This design proves naturally adapted to ceramic breeder assigned to very strict working conditions, and provides for any change in the thermal and heat transfer characteristics over the blanket lifetime. The final section of the paper is devoted to the evaluation of the heat load poloidal distribution and to the irradiation effects on first wall structural materials

  3. Analysis and discussion on reports of additional safety assessment of nuclear installations with respect to the Fukushima accident

    International Nuclear Information System (INIS)

    Sene, Monique; Sene, Raymond

    2011-11-01

    This document proposes an analysis of the reports made by the different operators of nuclear installations within the frame of a safety audit of the French nuclear installations with respect to the Fukushima accident. Operators (mainly AREVA, the CEA and EDF) were asked to perform additional safety assessments. In a first part, the conclusions of EDF reports are analysed regarding the seismic risk, the flooding risk, the situation of some specific sites (Fessenheim, Tricastin), other phenomena (rains, winds), loss of electricity supplies and of cooling systems, severe accidents, hydrogen issue, chemical hazards, subcontractors, crisis management. Conclusions of AREVA reports are analysed for the different sites (Tricastin, La Hague, MELOX factory, Romans factory). Conclusions of CEA reports are analysed for the different concerned installations (ATPu, Masurca, Osiris, Phenix, Jules Horowitz reactor). A second part proposes a global analysis of EDF's additional safety assessment reports regarding earthquake, flooding, other extreme natural phenomena, loss of electricity supplies and cooling system, subcontracting conditions, crisis management, and radiation protection organisation. AREVA's and CEA's reports are then analysed in terms of report structure and content, and for the different concerned sites

  4. Measurements of combined neutron and photon fluxes for the accurate characterization of the future Jules Horowitz irradiation reactor experimental conditions

    International Nuclear Information System (INIS)

    Fourmentel, D.

    2013-01-01

    A new Material Testing Reactor (MTR), the Jules Horowitz Reactor (JHR), is under construction at the CEA Cadarache (French Alternatives Energies and Atomic Energy Commission). From 2016 this new MTR will be a new facility for the nuclear research on materials and fuels. The quality of the experiments to be conducted in this reactor is largely linked to the good knowledge of the irradiation conditions. Since 2009, a new research program called IN-CORE1 'Instrumentation for Nuclear radiations and Calorimetry Online in Reactor' is under progress between CEA and Aix-Marseille University in the framework of a joint laboratory LIMMEX2. This program aims to improve knowledge of the neutron and photon fluxes in the RJH core, with one hand, an innovative instrumentation performing mapping of experimental locations, and on the other hand by coupling neutron flux, photon flux and thermal measurements. Neutron flux expected in the JHR core is about 10 15 n.cm -2 .s -1 and nuclear heating up to 20 W.g -1 for a nominal power of 100 MWth. One of the challenges is to identify sensors able to measure such fluxes in JHR experimental conditions and to determine how to analyse the signals delivered by these sensors with the most appropriate methods. The thesis is part of this ambitious program and aims to study the potential and the interest of the combination of radiation measurements in the prospect of a better assessment of the levels of neutron flux, gamma radiation and nuclear heating in the JHR experimental locations. The first step of IN-CORE program is to develop and operate an instrumented device called CARMEN-1 adapted to the mapping of the OSIRIS reactor, then to develop a second version called CARMEN-2 dedicated to experiments in the JHR core, especially for its start-up. This experiment was the opportunity to test all the radiation sensors which could meet the needs of JHR, including recently developed sensors. Reference neutron measurements are performed by activation

  5. Osiris and SOMBRERO inertial confinement fusion power plant designs

    International Nuclear Information System (INIS)

    Meier, W.R.; Bieri, R.L.; Monsler, M.J.

    1992-03-01

    Conceptual designs and assessments have been completed for two inertial fusion energy (IFE) electric power plants. The detailed designs and results of the assessment studies are presented in this report. Osiris is a heavy-ion-beam (HIB) driven power plant and SOMBRERO is a Krypton-Fluoride (KrF) laser-driven power plant. Both plants are sized for a net electric power of 1000 MWe

  6. Teaching Sodium Fast Reactors in CEA-INSTN

    International Nuclear Information System (INIS)

    Dufour, Ph.; Latgé, C.; Gicquel, L.

    2013-01-01

    Conclusion: Education and Training: - a key element for the future of the development of Sodium Fast Reactors, and more particularly ASTRID project. - a tool to create a new generation of skilled nuclear engineers in the field. - a unique mean to share basic knowledge, operational feedback, safety approaches. The two entities aimed to deliver Training sessions, i.e. Sodium School in Cadarache, and INSTN-Cadarache, are ready: - to conceive and propose tailored sessions, - to collaborate with other foreign Education and Training Entities

  7. Alexandre - a multi-project, multi-material and multi-technique action for an irradiation experiment in Osiris and post irradiation examination

    International Nuclear Information System (INIS)

    Averty, X.; Brachet, J.C.; Bertin, J.L.; Pizzanelli, J.P.; Rozenblum, F.

    1999-01-01

    This paper presents the data obtained on different classes of steels neutron irradiated at 325 deg C in pressurized water with a PWR-type chemistry. This irradiation, nicknamed 'Alexandre', took place in the OSIRIS reactor and finished in November 1999, for a maximum irradiation damage of ∼9 dpa. The preliminary results (up to 3.4 dpa), discussed in relation to chemical composition and initial metallurgical conditions, are listed below: - Evolution of the mechanical properties as a function of irradiation dose including the measurements of the Reduction-in-Area to failure by image analysis. - Comparison between out-of-pile and in-pile uniform corrosion. - Microstructural aspects (fractography, Transmission Electron Microscopy, and Small Angle Neutron Scattering measurements). - Post-irradiation evolution of residual. activity. (authors)

  8. The CEA's waste management strategy

    International Nuclear Information System (INIS)

    Behar, Ch.; Dall'ava, D.; Fillion, E.

    2011-01-01

    The CEA is tasked with carrying out certain research activities: within the Military Applications Division (DAM), research is focused on the nuclear deterrence and, within the Nuclear Energy Division, on developing the industrial nuclear systems of the future and optimising existing nuclear systems in partnership with EDF and AREVA. These major research and development themes entail a need for nuclear research and support facilities which must be maintained at a high level of performance and safety and, also, constantly upgraded to handle the research activities and programmes for which they are used. The CEA strategy is based on the right packaging of the radioactive liquid or solid waste into a form required for its transport, storage or disposal. The Caraibes software allows an efficient traceability of the waste packages. Most of the radioactive effluent processing stations of CEA are being upgraded

  9. Fission product releases at severe LWR accident conditions: ORNL/CEA measurements versus calculations

    Energy Technology Data Exchange (ETDEWEB)

    Andre, B.; Ducros, G.; Leveque, J.P. [CEA Centre d`Etudes de Grenoble, 38 (France). Dept. de Thermohydraulique et de Physique; Osborne, M.F.; Lorenz, R.A. [Oak Ridge National Lab., TN (United States); Maro, D. [CEA Centre d`Etudes de Fontenay-aux-Roses, 92 (France). Dept. de Protection de l`Environnement et des Installations

    1995-12-31

    Experimental programs in the United States and France have followed similar paths in supplying much of the data needed to analyze severe accidents. Both the HI/VI program, conducted at the Oak Ridge National Laboratory (ORNL) under the sponsorship of the U. S. Nuclear Regulatory Commission (NRC), and the HEVA/VERCORS program, supported by IPSN-Commissariat a l`Energie Atomique (CEA) and carried out at the Centre d`Etudes Nucleaires de Grenoble, have studied fission product release from light water reactor (LWR) fuel samples during test sequences representative of severe accidents. Recognizing that more accurate data, i.e., a better defined source term, could reduce the safety margins included in the rather conservative source terms originating from WASH-1400, the primary objective of these programs has been to improve the data base concerning fission product release and behavior at high temperatures. To facilitate the comparison, a model based on fission product diffusion mechanisms that was developed at ORNL and adapted with CEA experimental data is proposed. This CEA model is compared with the ORNL experimental data in a blind test. The two experimental programs used similar techniques in out-of-pile studies. Highly irradiated fuel samples were heated in radiofrequency induction furnaces to very high temperatures (up to 2700 K at ORNL and 2750 K at CEA) in oxidizing (H{sub 2}O), reducing (H{sub 2}) or mixed (H{sub 2}O+H{sub 2}) environments. The experimental parameters, which were chosen from calculated accident scenarios, did not duplicate specific accidents, but rather emphasized careful control of test conditions to facilitate extrapolation of the results to a wide variety of accident situations. This paper presents a broad and consistent database from ORNL and CEA release results obtained independently since the early 1980`S. A comparison of CORSOR and CORSOR Booth calculations, currently used in safety analysis, and the experimental results is presented and

  10. Annual report of the Association EURATOM-Cea 2004 (full report)

    International Nuclear Information System (INIS)

    Magaud, Ph.; Le Vagueres, F.

    2004-01-01

    This annual report summarizes activities performed by the EURATOM-Cea association in 2004. The activities carried out in the field 'physics integration' are mainly linked to neutral beam developments and to the development of diagnostic components. In particular, in-situ diagnostics of the plasma facing surface have been studied. Concerning 'vessel activities', the manufacturing of the ITER primary first wall panel by HIP forming has been investigated. A dummy mock-up was produced to validate the manufacturing feasibility. A new welding process able to improve welding productivity has been investigated, it is based on a hybrid laser/TIG process called Hybrid Laser Conduction Welding. A ITER first wall mock-up has been successfully manufactured using induction brazing. In the field 'magnets', EURATOM-Cea association was involved to provide input information for establishing the final dimension details of the ITER cryo-plant. EURATOM-Cea is also involved with the design of different parts of the ITER magnet system and the fabrication of mock-ups for some critical parts of the coils. In the field 'tritium breeding and materials', activities have mainly concerned the improvement and completion of the TBM (tritium breeding module) engineering design. A new batch of 1 kilogram of Li 2 TiO 3 pebbles with a size distribution in the range 0.6 to 0.8 mm was produced in 2004. Concerning materials, activities were focused on the EUROFER, a reduced activation martensitic steel. Activities performed in the field 'system studies' are dedicated to the power plant conceptual studies. In 2004, activities were focused on the reactor model AB, based on a helium-cooled lithium-lead blanket. (A.C.)

  11. 2004 annual report. Defense, safety, energy, information, health. CEA in the center of big European challenges; Rapport annuel 2004. Defense, securite, energie, information, sante. Le CEA au coeur des grands defis europeens

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This document is the 2004 annual report of the French atomic energy commission (CEA). It presents the R and D activities of the CEA in three main domains: 1 - defense and safety, maintaining perenniality of nuclear dissuasion and nuclear safety: supplying nuclear weapons to armies, maintaining dissuasion capability with the simulation program, sharing R and D means with the scientific community and the industrial world, designing and maintaining naval nuclear propulsion reactors, cleansing Marcoule and Pierrelatte facilities, monitoring treaties and fighting against proliferation and terrorism; 2 - energy, developing more competitive and cleaner energy sources: nuclear waste management, optimization of industrial nuclear activities, future nuclear systems and new energy technologies, basic research on energy, radiobiology and toxicology; 3 - information and health, valorizing industry thanks to technological research and supplying new tools for health and medical research: micro- and nano-technologies, software technologies, basic research for industrial innovation, nuclear technologies for health and bio-technologies. (J.S.)

  12. Lessons Learned from Preparing OSIRIS-REx Spectral Analog Samples for Bennu

    Science.gov (United States)

    Schrader, D. L.; McCoy, T. J.; Cody, G. D.; King, A. J.; Schofield, P. F.; Russell, S. S.; Connolly, H. C., Jr.; Keller, L. P.; Donaldson Hanna, K.; Bowles, N.; hide

    2017-01-01

    NASA's OSIRIS-REx sample return mission launched on September 8th, 2016 to rendezvous with B-type asteroid (101955) Bennu in 2018. Type C and B asteroids have been linked to carbonaceous chondrites because of their similar visible - to - near infrared (VIS-NIR) spectral properties [e.g., 1,2]. The OSIRIS-REx Visible and Infrared Spectrometer (OVIRS) and the Thermal Emission Spectrometer (OTES) will make spectroscopic observations of Bennu during the encounter. Constraining the presence or absence of hydrous minerals (e.g., Ca-carbonate, phyllosilicates) and organic molecules will be key to characterizing Bennu [3] prior to sample site selection. The goal of this study was to develop a suite of analog and meteorite samples and obtain their spectral properties over the wavelength ranges of OVIRS (0.4- 4.3 micrometer) and OTES (5.0-50 micrometer). These spectral data were used to validate the mission science-data processing system. We discuss the reasoning behind the study and share lessons learned.

  13. The CEA's waste management strategy; La strategie de gestion des dechets du CEA

    Energy Technology Data Exchange (ETDEWEB)

    Behar, Ch. [CEA Saclay, Dir. de l' Energie Nucleaire, 91 - Gif-sur-Yvette (France); Dall' ava, D. [CEA Saclay, Dir. de l' assainissement et du demantelement nucleaire, 91 - Gif-sur-Yvette (France); Fillion, E. [CEA Fontenay-aux-Roses, Direction de la protection et de la surete nucleaire, 92 (France)

    2011-02-15

    The CEA is tasked with carrying out certain research activities: within the Military Applications Division (DAM), research is focused on the nuclear deterrence and, within the Nuclear Energy Division, on developing the industrial nuclear systems of the future and optimising existing nuclear systems in partnership with EDF and AREVA. These major research and development themes entail a need for nuclear research and support facilities which must be maintained at a high level of performance and safety and, also, constantly upgraded to handle the research activities and programmes for which they are used. The CEA strategy is based on the right packaging of the radioactive liquid or solid waste into a form required for its transport, storage or disposal. The Caraibes software allows an efficient traceability of the waste packages. Most of the radioactive effluent processing stations of CEA are being upgraded

  14. Post irradiation examinations on UMo full-sized plates - IRIS2 experiment

    International Nuclear Information System (INIS)

    Huet, F.; Noirot, J.; Marelle, V.; Dubois, S.; Boulcourt, P.; Sacristan, P.; Naury, S.; Lemoine, P.

    2005-01-01

    IRIS2 irradiation was the last irradiation of 4 full sized plates launched by CEA for the French UMo group to test in which operating conditions the coarse porosity forms in the UMo/Al interaction product. IRIS2 consists in four plates with high uranium loading and U-7wt%Mo atomised powder irradiated up to 60 days at OSIRIS reactor in IRIS device at a peak power of 238 W.cm -2 . The results show that in the tested conditions pillowing of the plate started from a fission density over 2.10 21 fission.cm -3 . Moreover, they show that the fission products and impurities have a key-role in the origin of the excessive plate swelling. (author)

  15. Studies on the graphite rupture under irradiation induced strains

    International Nuclear Information System (INIS)

    Jouquet, G.; Berthion, Y.; L'Homme, A.

    1980-01-01

    Following the RMG experiments (failure of graphite by mechanical effect, i.e. under very high temperature gradient) an experimental program called RWG (Failure of Graphite by WIGNER effect) was initiated in 75 at C.E.A. 3 experiments have been already performed in the OSIRIS reactor at Saclay: RWG 01, 02 and 03. A 4th one, RWG04, is scheduled for the end of 79, may be in collaboration with GERMANY. The aim of the RWG experiments is to induce internal stresses in graphite blocks by irradiation at high temperature which would lead or not to their failure so one could bracket, as tightly as possible, the critical value for failure onset in given experimental conditions

  16. Comparison of Thermal Neutron Flux Measured by Uranium 235 Fission Chamber and Rhodium Self-Powered Neutron Detector in MTR

    International Nuclear Information System (INIS)

    Fourmentel, D.; Filliatre, P.; Barbot, L.; Villard, J.-F.; Lyoussi, A.; Geslot, B.; Malo, J.-Y.; Carcreff, H.; Reynard-Carette, C.

    2013-06-01

    Thermal neutron flux is one of the most important nuclear parameter to be measured on-line in Material Testing Reactors (MTRs). In particular two types of sensors with different physical operating principles are commonly used: self-powered neutron detectors (SPND) and fission chambers with uranium 235 coating. This work aims to compare on one hand the thermal neutron flux evaluation given by these two types of sensors and on the other hand to compare these evaluations with activation dosimeter measurements, which are considered as the reference for absolute neutron flux assessment. This study was conducted in an irradiation experiment, called CARMEN-1, performed during 2012 in OSIRIS reactor (CEA Saclay - France). The CARMEN-1 experiment aims to improve the neutron and photon flux and nuclear heating measurements in MTRs. In this paper we focus on the thermal neutron flux measurements performed in CARMEN-1 experiment. The use of fission chambers to measure the absolute thermal neutron flux in MTRs is not very usual. An innovative calibration method for fission chambers operated in Campbell mode has been developed at the CEA Cadarache (France) and tested for the first time in the CARMEN-1 experiment. The results of these measurements are discussed, with the objective to measure with the best accuracy the thermal neutron flux in the future Jules Horowitz Reactor. (authors)

  17. Making limb and nadir measurements comparable: A common volume study of PMC brightness observed by Odin OSIRIS and AIM CIPS

    Science.gov (United States)

    Benze, Susanne; Gumbel, Jörg; Randall, Cora E.; Karlsson, Bodil; Hultgren, Kristoffer; Lumpe, Jerry D.; Baumgarten, Gerd

    2018-01-01

    Combining limb and nadir satellite observations of Polar Mesospheric Clouds (PMCs) has long been recognized as problematic due to differences in observation geometry, scattering conditions, and retrieval approaches. This study offers a method of comparing PMC brightness observations from the nadir-viewing Aeronomy of Ice in the Mesosphere (AIM) Cloud Imaging and Particle Size (CIPS) instrument and the limb-viewing Odin Optical Spectrograph and InfraRed Imaging System (OSIRIS). OSIRIS and CIPS measurements are made comparable by defining a common volume for overlapping OSIRIS and CIPS observations for two northern hemisphere (NH) PMC seasons: NH08 and NH09. We define a scattering intensity quantity that is suitable for either nadir or limb observations and for different scattering conditions. A known CIPS bias is applied, differences in instrument sensitivity are analyzed and taken into account, and effects of cloud inhomogeneity and common volume definition on the comparison are discussed. Not accounting for instrument sensitivity differences or inhomogeneities in the PMC field, the mean relative difference in cloud brightness (CIPS - OSIRIS) is -102 ± 55%. The differences are largest for coincidences with very inhomogeneous clouds that are dominated by pixels that CIPS reports as non-cloud points. Removing these coincidences, the mean relative difference in cloud brightness reduces to -6 ± 14%. The correlation coefficient between the CIPS and OSIRIS measurements of PMC brightness variations in space and time is remarkably high, at 0.94. Overall, the comparison shows excellent agreement despite different retrieval approaches and observation geometries.

  18. Nuclear systems of the future: international forum generation 4 and research and development projects at the Cea; Systemes nucleaires du futur: forum international generation 4 et projets de R et D du CEA

    Energy Technology Data Exchange (ETDEWEB)

    Carre, F

    2003-07-01

    To advance nuclear energy to meet future energy needs, ten countries have agreed to develop a future generation of nuclear energy systems, known as Generation 4. A technology road map to guide the Generation 4 effort was begun. This document presents the goals for these nuclear systems and the research programs of the Cea on the gas technology, GT-MHR, VHTR and GFR and the other systems as sodium Fast Neutron reactors, supercritical water and space nuclear. (A.L.B.)

  19. Fifty years of particle physics at the CEA

    International Nuclear Information System (INIS)

    Turlay, R.

    1997-01-01

    A historical review of researches at the CEA (and more particularly at Saclay) in particle physics, is presented. Contributions in themes such as polarized targets, bubble chambers, classic and superconductive magnets, etc. resulted in cooperation to the design of various machines such as Van de Graaff accelerator, cyclotron, Saturne, etc. Collaborations between CEA and CERN had led to numerous experiments in high energy physics, such as electronic experiments with the SPS accelerator. CEA was also involved in the intermediate boson discovery on the SppS collision apparatus, and is participating in two CERN's programs, neutrino physics (NOMAD) and CP violation (NA48). CEA is also collaborating with Russian, German and American laboratories in these domains

  20. The CEA/DRN innovative R and D programme: significant studies on passive systems

    International Nuclear Information System (INIS)

    Fiorini, G.L.; Magistris, F. de; Dumaz, P.; Gautier, G.M.; Pignatel, J.F.; Richard, P.

    1999-01-01

    The work on passive systems is an essential item of the R and D programme for future reactors; it is structured following four main guidelines: Research, and validation of innovative solutions for the safety functions achievement; An enlarged assessment of the performances of passive systems; Extension of the data base and of the tools qualification range; Assessment of new plant operation modes. After a recalling on the general framework, the paper describes, following these guidelines, the status of the art of the main corresponding programmes within CEA/DRN. (author)

  1. Irradiation tests of U3Si2-Al fuels up to very high fission densities

    International Nuclear Information System (INIS)

    Nuding, M.; Boening, K.

    2001-01-01

    The new research reactor of the Munich Technical University (TUM), the FRM-II, will have U 3 Si 2 -Al as the fuel. This fuel is considered qualified and optimally usable in the light of findings obtained in the RERTR program (Reduced Enrichment for Research and Test Reactors). The RERTR program was conducted to develop new fuel for the use of low enriched uranium (LEU) in research reactors. As the unique properties of the FRM-II in research and application are based also on achieving a very compact reactor core with highly enriched uranium (HEU), additional irradiation tests were performed on the basis of the RERTR program. They were run in close cooperation with the French Commissariat a l'Energie Atomique (CEA) in its SILOE and OSIRIS facilities, among others. After extensive evaluation, also of other studies, these tests confirm the RERTR findings about fuel swelling behavior and, consequently, the suitability of U 3 Si 2 -Al (HEU) for use in the compact core of the FRM-II. (orig.) [de

  2. CEA - 2011 annual report, 2011 financial statement

    International Nuclear Information System (INIS)

    2012-06-01

    The first report, available both in French and English, presents the different current programs: low carbon energies and associated fundamental researches, global defence and safety and associated researches, information technologies and associated researches, technologies for health and associated fundamental researches, very large research infrastructures and associated fundamental researches. It then addresses the CEA openness: assessment, teaching and training, research valorisation, awards, and the support to various programs: steering activity by the CEA, human resources, international relationships, communication, risk management, information systems. The last part describes the CEA organisation. The second report presents the different financial and accounting data and tables

  3. Observation on CEA and IL-6 contents in gastric juice

    International Nuclear Information System (INIS)

    Jiang Zhonglin

    2003-01-01

    Objective: To study the changes of CEA and IL-6 contents in blood and gastric juice in patients with gastric cancer and gastritis. Methods: CEA and IL-6 contents in blood and gastric juice were measured with RIA in 60 patients and 30 controls. Results: Gastric juice CEA and IL-6 contents in patients with gastric carcinoma were significantly higher than those in the controls (p < 0.001), however, CEA and IL-6 contents in patients with gastritis and controls were not much different. Conclusion: Gastric juice CEA and IL-6 assay is of diagnostic significance in patients with gastric malignant tumor

  4. CEA Annual progress report 1986

    International Nuclear Information System (INIS)

    1987-01-01

    This annual report presents the general organization of the CEA, the international relations and politics in nuclear field, the activities (military application, nuclear applied research, ANDRA (National Agency for Radioactive Waste Management), nuclear safety and protection, fundamental research, applied research other than nuclear), the industrial group; among topics about men and means, the budget execution of the public establishment of research. In annex, the nuclear power plants around the world and the principal legislative texts related to CEA or atomic energy published in 1986 [fr

  5. Big reorganisation at the CEA; [structural reorganisation and reform of management methods within the CEA; CEA document on civil nuclear energy policy research

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    Following the recommendations of a report prepared by the Director General, CEA is to be reorganised to clarify the division of responsibility within the CEA and to increase its adaptability and openness to the outside world. The management structures have been simplified and two large institutes of the Commissariat, the Institute of Industrial Research and Development and the Institute of Fundamental Research have been disbanded and their activities reallocated to six smaller operational directorates. Seven functional directorates have been created to cover communications, finance, defence issues, manpower, international relations, planning and secretariat. An outline of the new structure is given and explained. (UK)

  6. Functional approaches: a new view of nuclear reactors management

    International Nuclear Information System (INIS)

    Papin, B.

    2000-01-01

    Since many years a research program on the future reactors command, has been decided by the CEA, in collaboration with EDF and Framatome. This program aims to enhance the reactor safety by a better control of the installation in any exploitation situations. The paper presents the state of the art and the first reflexions. (A.L.B.)

  7. Osiris-Rex and Hayabusa2 Sample Cleanroom Design and Construction Planning at NASA-JSC

    Science.gov (United States)

    Righter, Kevin; Pace, Lisa F.; Messenger, Keiko

    2018-01-01

    Final Paper and not the abstract is attached. The OSIRIS-REx asteroid sample return mission launched to asteroid Bennu September 8, 2016. The spacecraft will arrive at Bennu in late 2019, orbit and map the asteroid, and perform a touch and go (TAG) sampling maneuver in July 2020. After confirma-tion of successful sample stowage, the spacecraft will return to Earth, and the sample return capsule (SRC) will land in Utah in September 2023. Samples will be recovered from Utah and then transported and stored in a new sample cleanroom at NASA Johnson Space Center in Houston. All curation-specific ex-amination and documentation activities related to Ben-nu samples will be conducted in the dedicated OSIRIS-REx sample cleanroom to be built at NASA-JSC.

  8. Carcinoembryonic antigen (CEA) as tumor marker in lung cancer.

    Science.gov (United States)

    Grunnet, M; Sorensen, J B

    2012-05-01

    The use of CEA as a prognostic and predictive marker in patients with lung cancer is widely debated. The aim of this review was to evaluate the results from studies made on this subject. Using the search words "CEA", "tumor markers in lung cancer", "prognostic significance", "diagnostic significance" and "predictive significance", a search was carried out on PubMed. Exclusion criteria was articles never published in English, articles before 1981 and articles evaluating tumor markers in lung cancer not involving CEA. Initially 217 articles were found, and 34 were left after selecting those relevant for the present study. Four of these included both Non-Small Cell Lung Cancer (NSCLC) and Small Cell Lung Cancer (SCLC) patients, and 31 dealt solely with NSCLC patients. Regarding SCLC no studies showed that serum level of CEA was a prognostic marker for overall survival (OS). The use of CEA serum level as a prognostic marker in NSCLC was investigated in 23 studies and the use of CEA plasma level in two. In 18 (17 serum, 1 plasma) of these studies CEA was found to be a useful prognostic marker for either OS, recurrence after surgery or/and progression free survival (PFS) in NSCLC patients. Interestingly, an overweight of low stage (stage I-II) disease and adenocarcinoma (AC) patients were observed in this group. The remaining 7 studies (6 serum, 1 plasma) contained an overweight of patients with squamous carcinoma (SQ). One study found evidence for that a tumor marker index (TMI), based on preoperative CEA and CYFRA21-1 serum levels, is useful as a prognostic marker for OS in NSCLC. Six studies evaluated the use of CEA as a predictive marker for risk of recurrence and risk of death in NSCLC patients. Four of these studies found, that CEA was useful as a predictive marker for risk of recurrence and risk of death measured over time. No studies found CEA levels useful as a diagnostic marker for lung cancer. With regard to NSCLC the level of CEA measured in tumor tissue in

  9. RHTF 2, a 1200 MWe high temperature reactor

    International Nuclear Information System (INIS)

    Brisbois, Jacques

    1978-01-01

    After having adapted to French conditions the 1160 MWe G.A.C. reactor, Commissariat a l'Energie Atomique and French Industry have decided to design an High Temperature Reactor 1200 MWe based on the G.A.C. technology and taking into account the point of view of Electricite de France and the experience of C.E.A. and industry on the gas cooled reactor technology. The main objective of this work is to produce a reactor design having a low technical risk, good operability, with an emphasis on the safety aspects easing the licensing problems

  10. Use of OsiriX in developing a digital radiology teaching library

    International Nuclear Information System (INIS)

    Shamshuddin, S.; Matthews, H.R.

    2014-01-01

    Widespread adoption of digital imaging in clinical practice and for the image-based examinations of the Royal College of Radiologists has created a desire to provide a digital radiology teaching library in many hospital departments around the UK. This article describes our experience of using OsiriX software in developing digital radiology teaching libraries

  11. Minutes of the 2. Meeting of the WPRS / EGRPANS / Sodium Fast Reactor Task Force (SFR)

    International Nuclear Information System (INIS)

    Ivanov, Evgeny; Kereszturi, Andras; Pataki, I.; Tota, A.; Vertes, P.; Kim, Taek K.; Taiwo, T.A.; Kugo, Teruhiko; Lee, Yi Kang; Messaoudi, Nadia; Michel-Sendis, Franco; ); Pascal, Vincent; Buiron, Laurent; Varaine, Frederic; Ponomarev, Alexander

    2012-01-01

    Five organizations (SCK/CEN, KIT, KFKI, CEA, ANL) participated in the Sodium-cooled fast reactor (SFR) Benchmark calculations and all results were collected and compiled by CEA and ANL. The compiled results of the large size cores and medium size cores were presented by V. Pascal (CEA) and T. K. Kim (ANL), respectively. Separately, A. Kereszturi presented his recently updated results. It was observed that there is wide variation in core multiplication factor, kinetics parameters, and reactivity feedback coefficients. In particular, compared to the CEA results, ANL calculated smaller k-eff, Doppler constant, but higher sodium void worth and control rod worth. The core modeling issue (heterogeneous vs. homogeneous) and solution method (diffusion vs. transport) were identified as the potential reasons of these discrepancies, including the minor impacts from the depletion chains and lumped fission product modeling. All participants agreed that additional investigation was needed to identify the reasons of these discrepancies. In addition, V. Pascal presented the informative notes of the reactivity feedback calculations methodology proposed by CEA. This document brings together the 5 presentations (slides) given at this meeting: 1 - SFR Task Force : Core behavior during transient as a function of power size and fuel nature (L. Buiron, V. Pascal, F. Varaine); 2 - Sodium Fast Reactor core Feedback and Transient response (SFRFT) Expert Group: preliminary benchmark results for large cores (L. Buiron, V. Pascal, F. Varaine); 3 - Numerical Benchmark Results for 1000 MWth Sodium-cooled Fast Reactor (T.K. Kim and T.A. Taiwo); 4 - Preliminary results of the WPRS Sodium-Cooled Fast Reactor Benchmark problems (A. Kereszturi, I. Pataki, A. Tota, P. Vertes); 5 - SFR Task Force : proposal for Feedback coefficients estimation methodology (L. Buiron, V.Pascal, F. Varaine)

  12. Shutdown channels and fitted interlocks in atomic reactors; Chaines de securite et verrouillages installes sur les piles atomiques

    Energy Technology Data Exchange (ETDEWEB)

    Furet, J; Landauer, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1968-07-01

    This catalogue consists of tables (one per reactor) giving the following information: number and type of detectors, range of the shutdown channels, nature of the associated electronics, thresholds setting off the alarms, fitted interlocks. These cards have been drawn up with a view to an examination of the reactors safety by the 'Reactor Safety Sub-Commission', they take into account the latest decisions. The reactors involved in this review are: Azur, Cabri, Castor-Pollux, Cesar-Marius-2, Edf-2, EL3, EL4, Eole, G1, G2-G3, Harmonie, Isis, Masurca, Melusine, Minerve, Osiris, Pegase, Peggy, PAT, Rapsodie, SENA, Siloe, Siloette, Triton-Nereide, and Ulysse. (authors) [French] Ce catalogue est compose d'un ensemble de tableaux (a raison de un tableau par pile) donnant les renseignements suivants: nombre et nature des detecteurs, dynamique des chaines, nature de l'electronique associee, seuils provoquant des actions de securite, verrouillages installes. Ces fiches ont ete etablies en vue de l'examen de la securite des piles par la 'Sous-Commission de Surete des Piles', et tiennent compte des decisions de celle-ci. Les reacteurs concernes sont: Azur, Cabri, Cator-Pollux, Cesar-Marius-2, Edf-2, EL3, EL4, Eole, G1, G2-G3, Harmonie, Isis, Masurca, Melusine, Minerve, Osiris, Pegase, Peggy, PAT, Rapsodie, SENA, Siloe, Siloette, Triton-Nereide, et Ulysse. (auteurs)

  13. Improved measurements of thermal power and control rods using multiple detectors at the TRIGA Mark II reactor in Ljubljana

    International Nuclear Information System (INIS)

    Zerovnik Gasper; Snoj Luka; Trkov Andrej; Barbot Loic; Fourmentel Damien; Villard Jean-Francois

    2013-06-01

    The aim of the current bilateral project between CEA Cadarache and JSI is to improve the accuracy of the online thermal power monitoring at the JSI TRIGA reactor. Simultaneously, a new wide range multichannel acquisition system for fission chambers, recently developed by CEA, is tested. In the paper, calculational and experimental power calibration methods are described. The focus is on use of multiple detectors in combination with pre-calculated and pre-measured control rod- position-dependent correction factors to improve the reactor power reading. The system will be implemented and tested at the JSI TRIGA reactor in 2014. (authors)

  14. Evaluation of the concrete shield compositions from the 2010 criticality accident alarm system benchmark experiments at the CEA Valduc SILENE facility

    International Nuclear Information System (INIS)

    Miller, Thomas Martin; Celik, Cihangir; Dunn, Michael E; Wagner, John C; McMahan, Kimberly L; Authier, Nicolas; Jacquet, Xavier; Rousseau, Guillaume; Wolff, Herve; Savanier, Laurence; Baclet, Nathalie; Lee, Yi-kang; Trama, Jean-Christophe; Masse, Veronique; Gagnier, Emmanuel; Naury, Sylvie; Blanc-Tranchant, Patrick; Hunter, Richard; Kim, Soon; Dulik, George Michael; Reynolds, Kevin H.

    2015-01-01

    In October 2010, a series of benchmark experiments were conducted at the French Commissariat a l'Energie Atomique et aux Energies Alternatives (CEA) Valduc SILENE facility. These experiments were a joint effort between the United States Department of Energy Nuclear Criticality Safety Program and the CEA. The purpose of these experiments was to create three benchmarks for the verification and validation of radiation transport codes and evaluated nuclear data used in the analysis of criticality accident alarm systems. This series of experiments consisted of three single-pulsed experiments with the SILENE reactor. For the first experiment, the reactor was bare (unshielded), whereas in the second and third experiments, it was shielded by lead and polyethylene, respectively. The polyethylene shield of the third experiment had a cadmium liner on its internal and external surfaces, which vertically was located near the fuel region of SILENE. During each experiment, several neutron activation foils and thermoluminescent dosimeters (TLDs) were placed around the reactor. Nearly half of the foils and TLDs had additional high-density magnetite concrete, high-density barite concrete, standard concrete, and/or BoroBond shields. CEA Saclay provided all the concrete, and the US Y-12 National Security Complex provided the BoroBond. Measurement data from the experiments were published at the 2011 International Conference on Nuclear Criticality (ICNC 2011) and the 2013 Nuclear Criticality Safety Division (NCSD 2013) topical meeting. Preliminary computational results for the first experiment were presented in the ICNC 2011 paper, which showed poor agreement between the computational results and the measured values of the foils shielded by concrete. Recently the hydrogen content, boron content, and density of these concrete shields were further investigated within the constraints of the previously available data. New computational results for the first experiment are now available

  15. Osiris-REx Spacecraft Current Status and Forward Plans

    Science.gov (United States)

    Messenger, Scott; Lauretta, Dante S.; Connolly, Harold C., Jr.

    2017-01-01

    The NASA New Frontiers OSIRIS-REx spacecraft executed a flawless launch on September 8, 2016 to begin its 23-month journey to near-Earth asteroid (101955). The primary objective of the OSIRIS-REx mission is to collect and return to Earth a pristine sample of regolith from the asteroid surface. The sampling event will occur after a two-year period of remote sensing that will ensure a high probability of successful sampling of a region on the asteroid surface having high science value and within well-defined geological context. The OSIRIS-REx instrument payload includes three high-resolution cameras (OCAMS), a visible and near-infrared spectrometer (OVIRS), a thermal imaging spectrometer (OTES), an X-ray imaging spectrometer (REXIS), and a laser altimeter (OLA). As the spacecraft follows its nominal outbound-cruise trajectory, the propulsion, power, communications, and science instruments have undergone basic functional tests, with no major issues. Outbound cruise science investigations include a search for Earth Trojan asteroids as the spacecraft approaches the Sun-Earth L4 Lagrangian point in February 2017. Additional instrument checkouts and calibrations will be carried out during the Earth gravity assist maneuver in September 2017. During the Earth-moon flyby, visual and spectral images will be acquired to validate instrument command sequences planned for Bennu remote sensing. The asteroid Bennu remote sensing campaign will yield high resolution maps of the temperature and thermal inertia, distributions of major minerals and concentrations of organic matter across the asteroid surface. A high resolution 3d shape model including local surface slopes and a high-resolution gravity field will also be determined. Together, these data will be used to generate four separate maps that will be used to select the sampling site(s). The Safety map will identify hazardous and safe operational regions on the asteroid surface. The Deliverability map will quantify the accuracy

  16. Oscillation experiments techniques in CEA Minerve experimental reactor

    Energy Technology Data Exchange (ETDEWEB)

    Antony, M.; Di-Salvo, J.; Pepino, A.; Bosq, J. C.; Bernard, D.; Leconte, P.; Hudelot, J. P.; Lyoussi, A. [CEA CADARACHE, DEN/DER/SPEx, 13108 Saint Paul-lez-Durance (France)

    2009-07-01

    This paper deals with experiments in the Minerve pool Zero Power Reactor. Minerve is mainly devoted to neutronics studies, in view to improve the calculation routes by reducing the uncertainties of the experimental databases for nuclides arising in plutonium and wastes management. Minerve experimental measurement programs are performed by using the oscillation technique. This experimental technique consists in a periodic insertion and extraction of samples containing the nuclide of interest in a well characterized neutron spectrum. The reactivity variation of the sample is compensated by a calibrated rotary automatic pilot using cadmium sectors. The normal accuracy for measurements of small-worth samples in Minerve by using such a technique is about 3% for absolute reactivity worth, including the uncertainties on the material balance and on the calibration step. Reactivity effects of less than 1.5 cent can be measured. The OSMOSE and the OCEAN programs have been carried out since 2005 and will last until 2011. These programs aim at improving, in different neutron spectra, the absorption cross sections of respectively a majority of the separated heavy nuclides from {sup 232}Th to {sup 245}Cm appearing during the reactor and the fuel cycle physics, and of current and future types of absorbers as Gd, Hf, Er, Dy and Eu. (authors)

  17. Carcinoembryonic antigen (CEA) as tumor marker in lung cancer

    DEFF Research Database (Denmark)

    Knudsen, Mie Grunnet; Sorensen, J B

    2012-01-01

    The use of CEA as a prognostic and predictive marker in patients with lung cancer is widely debated. The aim of this review was to evaluate the results from studies made on this subject. Using the search words "CEA", "tumor markers in lung cancer", "prognostic significance", "diagnostic...... significance" and "predictive significance", a search was carried out on PubMed. Exclusion criteria was articles never published in English, articles before 1981 and articles evaluating tumor markers in lung cancer not involving CEA. Initially 217 articles were found, and 34 were left after selecting those...... relevant for the present study. Four of these included both Non-Small Cell Lung Cancer (NSCLC) and Small Cell Lung Cancer (SCLC) patients, and 31 dealt solely with NSCLC patients. Regarding SCLC no studies showed that serum level of CEA was a prognostic marker for overall survival (OS). The use of CEA...

  18. From Melusine to MINATEC. 1956-2006. 50 years of CENG history, which has become CEA-Grenoble

    International Nuclear Information System (INIS)

    Ballu, Y.

    2006-01-01

    This book, fully illustrated, relates 50 years of history of the nuclear research center of Grenoble (CENG), which is today the CEA-Grenoble. The book follows the chronological order, from the building up of the research center and of the Melusine reactor in the 1950's to the first steps in microelectronic research in the 1960's and to the creation in 2003 of MINATEC the first European research center on micro- and nano-technologies. (J.S.)

  19. Development of electro-magnetic pump for the ASTRID Sodium-cooled Fast Reactor

    International Nuclear Information System (INIS)

    Suzuki, Tetsu; Aizawa, Rie; Wakasaki, Shingo; Dechelette, Frank; Benoit, Fabrice

    2017-01-01

    In the framework of the SFR (Sodium-cooled Fast Reactor) prototype called ASTRID (Advance Sodium Technological Reactor for Industrial Demonstration), the large capacity Electro-Magnetic Pumps (EMP) as main circulating pumps on the intermediate sodium circuits has been considered instead of mechanical pumps by CEA. The use of EMP has several decisive technological merits compared with mechanical pump in the reactor design, operation and maintenance. Nevertheless, some theoretical and technological developments have to be carried out in order to validate the design tools which take Magneto Hydro Dynamic (MHD) phenomena into account and the applicability of the EMP to the steady state and transient operating conditions of ASTRID. To move forward to developments, a collaboration agreement between the CEA and TOSHIBA Corporation was made and entered into to carry out a joint work program on the EMP for ASTRID design and development. CEA performed the theoretical analysis, and the EMP experimental model is constructed by CEA to support these theoretical developments. This model consists of a middle-size annular EMP for the liquid metal sodium. The various testing program using this model has been started in 2016. TOSHIBA performed the examination of design specification for ASTRID, an electromagnetic design, a structural design and various analyses. The structure design has been examined the placement of the sodium boundary and the withstand pressure, etc. And, if the thicknesses of the structure increase for withstanding pressure, the pump efficiency falls because the loss of the electromagnetic force increases. Therefore the balance between withstanding pressure and the efficiency has been considered by an electromagnetism design. This paper presents the design studies and experimental activities for the EMP development in the framework of the CEA-TOSHIBA collaborations. (author)

  20. A gamma heating calculation methodology for research reactor application

    International Nuclear Information System (INIS)

    Lee, Y.K.; David, J.C.; Carcreff, H.

    2001-01-01

    Gamma heating is an important issue in research reactor operation and fuel safety. Heat deposition in irradiation targets and temperature distribution in irradiation facility should be determined so as to obtain the optimal irradiation conditions. This paper presents a recently developed gamma heating calculation methodology and its application on the research reactors. Based on the TRIPOLI-4 Monte Carlo code under the continuous-energy option, this new calculation methodology was validated against calorimetric measurements realized within a large ex-core irradiation facility of the 70 MWth OSIRIS materials testing reactor (MTR). The contributions from prompt fission neutrons, prompt fission γ-rays, capture γ-rays and inelastic γ-rays to heat deposition were evaluated by a coupled (n, γ) transport calculation. The fission product decay γ-rays were also considered but the activation γ-rays were neglected in this study. (author)

  1. Gas-cooled reactor thermal-hydraulics using CAST3M and CRONOS2 codes

    International Nuclear Information System (INIS)

    Studer, E.; Coulon, N.; Stietel, A.; Damian, F.; Golfier, H.; Raepsaet, X.

    2003-01-01

    The CEA R and D program on advanced Gas Cooled Reactors (GCR) relies on different concepts: modular High Temperature Reactor (HTR), its evolution dedicated to hydrogen production (Very High Temperature Reactor) and Gas Cooled Fast Reactors (GCFR). Some key safety questions are related to decay heat removal during potential accident. This is strongly connected to passive natural convection (including gas injection of Helium, CO 2 , Nitrogen or Argon) or forced convection using active safety systems (gas blowers, heat exchangers). To support this effort, thermal-hydraulics computer codes will be necessary tools to design, enhance the performance and ensure a high safety level of the different reactors. Accurate and efficient modeling of heat transfer by conduction, convection or thermal radiation as well as energy storage are necessary requirements to obtain a high level of confidence in the thermal-hydraulic simulations. To achieve that goal a thorough validation process has to ve conducted. CEA's CAST3M code dedicated to GCR thermal-hydraulics has been validated against different test cases: academic interaction between natural convection and thermal radiation, small scale in-house THERCE experiments and large scale High Temperature Test Reactor benchmarks such as HTTR-VC benchmark. Coupling with neutronics is also an important modeling aspect for the determination of neutronic parameters such as neutronic coefficient (Doppler, moderator,...), critical position of control rods...CEA's CAST3M and CRONOS2 computer codes allow this coupling and a first example of coupled thermal-hydraulics/neutronics calculations has been performed. Comparison with experimental data will be the next step with High Temperature Test Reactor experimental results at nominal power

  2. The CEA-Industrie Group of Companies

    International Nuclear Information System (INIS)

    1988-01-01

    The 1988 financial and technological status of the CEA-Industry Group of Companies is summarized. The activities, technological innovations, and areas of development perspectives of the CEA-Industry Group of Companies, chiefly concentrated in fields relating to nuclear energy, are described. The principal business sectors of the group involve nuclear fuel cycle, nuclear plants and maintenance, computer applications and life science. Some activities of the group are extended to management, construction and financial fields

  3. Nuclear toxicology at CEA

    International Nuclear Information System (INIS)

    Giustranti, C.

    2001-01-01

    CEA (French commission of atomic energy) has launched a new program dedicated to the study of the transfer of heavy metals and some radionuclides from environment to living beings. The substances that will be studied, are those that are involved in research, medical activities, and in nuclear industry. It means iodine, technetium, trans-uranides (uranium and plutonium), fission products (iodine, cesium), carbon, cobalt, boron and beryllium. This program is composed of 2 axis: the first one concerns the bio-geo-chemical cycles that are involved in transfer and the second axis deals with the detoxication processes that appear in animal and man cells. This program will rely on the strong competencies of CEA in chemistry, radiochemistry, biology, physiology and toxicology. (A.C.)

  4. CEA - Annual report 2006

    International Nuclear Information System (INIS)

    2006-01-01

    The CEA, a prominent player in research development and innovation, is active in 3 main areas: energy, health care and information technology and defense and security. This annual report presents the CEA activity for the year 2006 in these three main areas: Science and technology working for nuclear deterrence and global security (the simulation programs, the nuclear warheads, the nuclear propulsion, the decommissioning, the fighting against nuclear proliferation and monitoring international treaties, the global security); health and information technology (micro and nano technologies and systems); energy from nuclear fission and fusion and other technologies that do not emit greenhouse gases (progress for the nuclear industry, sustainable management of radioactive materials and waste, nuclear systems of the future, new energy technologies). (A.L.B.)

  5. Origin and development of the new U-Mo nuclear fuel

    International Nuclear Information System (INIS)

    Boyard, M.; Languille, A.; Thomasson, J.; Hamy, J.M.

    2002-01-01

    Historically most research reactors have used highly enriched nuclear fuels (enrichment > 90 %). Since 1977 the non-proliferation policy has imposed to convert these reactors to far less enriched fuels (< 20 %). An international consensus has evolved towards a nuclear fuel with an enrichment factor of 19,75 %, this fuel is made of a powdered U-Mo alloy scattered in an aluminium die. The external dimensions and the cladding materials of the fuel plate are unchanged in order to minimize development and qualification costs. The U-Mo fuel is expected to maintain or even to increase the performance of reactors and to allow the processing of spent fuels in the same installations as those used for fuels issuing from power plants. Cea, Cogema, Cerca, Framatome, and Technicatome have shared their technical means, their know-how and their financial resources to develop this new nuclear fuel. 2006 is the contract date by which American authorities will stop repatriating the ancient spent fuel (uranium silicide) from research reactors so it is imperative to make available by this date a new nuclear fuel with a satisfactory end of cycle. This article also presents the French program of qualification of the U-Mo fuel. 2 series of irradiation have already been performed, one (Isis-1) in Osiris reactor (Saclay, France) and the second (Umus) in HFR (Petten, Netherlands). A clad failure has led to stop the Umus experiment. 2 new series of irradiation are scheduled to start in 2002. In a parallel way, in the framework of the design of the RJH (Jules Horowitz reactor) Cea will soon perform irradiation of U-Mo fuel plates in BR2 (Mol, Belgium). (A.C.)

  6. Low power modular power generating reactors or Small Modular Reactors (SMR)

    International Nuclear Information System (INIS)

    Chenais, Jacques

    2016-01-01

    Electronuclear reactors were small reactors at the beginning, and then tend to be always bigger and more powerful, but since some recent times, several countries specialized in reactor design and fabrication (USA, Russia, China, and South Korea) have been developing Small Modular Reactors (SMR) of less than 300 MW. As France has already produced feasibility studies and is about to launch a SMR development programme, the author comments some specific aspects of this new architecture of reactors, characterises the targeted markets, gives an overview of the various more or less advanced existing concepts: a floating barge in Russia, the SMART 100 MW project in South Korea, several concepts in the USA (the mPower 125 MW, the NuScale 45 MW, the Westinghouse 225 MW, and the HI-SMUR 160 MW projects), the ACP 100 MW in China, the CAREM 27 MW in Argentina. French projects developed by the CEA, EDF, Areva and DCNS are then presented

  7. Corrigendum to small power and heat generation systems on the basis of propulsion and innovative reactor technologies (IAEA-TECDOC-1172)

    International Nuclear Information System (INIS)

    2000-09-01

    Full text: - Footnote 1 on page 4 should read: '' 1 The results of the feasibility studies were presented by BARC at the meeting, but no paper was provided for publication in these proceedings.'' - On page 5, footnote 2 should be added to the following paragraph: ''CEA and TECHNICATOM (France) have about 200 reactor-years of experience from propulsion and small experimental reactors. Special design features for a future small reactor are formulated as follows 2 :'' ('' 2 At the meeting, these features were presented by CEA, Cadarache, but no paper was provided for publication in these proceedings.'')

  8. Corrigendum to small power and heat generation systems on the basis of propulsion and innovative reactor technologies (IAEA-TECDOC-1172)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-09-01

    Full text: - Footnote 1 on page 4 should read: ''{sup 1}The results of the feasibility studies were presented by BARC at the meeting, but no paper was provided for publication in these proceedings.'' - On page 5, footnote 2 should be added to the following paragraph: ''CEA and TECHNICATOM (France) have about 200 reactor-years of experience from propulsion and small experimental reactors. Special design features for a future small reactor are formulated as follows{sup 2}:'' (''{sup 2} At the meeting, these features were presented by CEA, Cadarache, but no paper was provided for publication in these proceedings.'')

  9. How the CEA sorts out its certifications

    International Nuclear Information System (INIS)

    Lembezat, C.

    2011-01-01

    In order to better manage its numerous certifications, the French CEA decided to implement an integrated management system. It aims at simplifying these certifications, at sharing best practices, and at obtaining a better efficiency. For this project, i.e. the management of quality, safety and environment, the CEA asked for the support of experts in integrated complex system management

  10. Life sciences at CEA

    International Nuclear Information System (INIS)

    2000-01-01

    This paper presents briefly the organization of the - Direction des Sciences du Vivant - of french atomic energy commission (Commissariat a l'Energie Atomique (CEA)) and their main axes of research (F.M)

  11. CEA A BIOCHEMICAL MARKER FOR DIAGNOSIS AND PROGNOSIS OF GASTROINTESTINAL CANCER

    Directory of Open Access Journals (Sweden)

    Prathibha

    2016-02-01

    Full Text Available Serum tumor markers (TM are widely used for diagnosis and monitoring of treatment of cancer. Carcinoembryonic Antigen (CEA is one of the most widely investigated tumor markers in gastrointestinal (GI cancers. Estimation of circulating tumor markers is a non- invasive quantitative method. Serum levels of CEA were studied for diagnosis and prognosis of gastrointestinal malignancies. 140 subjects were undertaken out of which 35 normal and remaining 105 were GI cancer patients. Serum levels of CEA were analyzed by Enzyme Linked Immunosorbent Assay (ELISA. Result of serum CEA levels of the GI cancer patients and normal subjects were analyzed statistically. It was observed that there was significant increase in (P <0.01 in CEA levels of oesophagus, stomach and colon cancer patients as compared to normal subjects. The levels of CEA decreased significantly after the surgery but the decrease in levels of CEA was not up to the levels as normal control subjects.

  12. Numerical benchmark for the deep-burn modular helium-cooled reactor (DB-MHR)

    International Nuclear Information System (INIS)

    Taiwo, T. A.; Kim, T. K.; Buiron, L.; Varaine, F.

    2006-01-01

    Numerical benchmark problems for the deep-burn concept based on the prismatic modular helium-cooled reactor design (a Very High Temperature Reactor (VHTR)) are specified for joint analysis by U.S. national laboratories and industry and the French CEA. The results obtained with deterministic and Monte Carlo codes have been inter-compared and used to confirm the underlying feature of the DB-MHR concept (high transuranics consumption). The results are also used to evaluate the impact of differences in code methodologies and nuclear data files on the code predictions for DB-MHR core physics parameters. The code packages of the participating organizations (ANL and CEA) are found to give very similar results. (authors)

  13. Overview of CNES-CEA joint programme on space nuclear Brayton systems

    International Nuclear Information System (INIS)

    Carre, F.; Proust, E.; Chaudourne, S.; Keirle, P.; Tilliette, Z.; Vrillon, B.

    1990-01-01

    In 1982, a cooperative programme on space nuclear power systems was initiated between the French Centre National d'Etudes Spatiales (CNES) and the Commissariat a l'Energie Atomique (CEA), to assess the feasibility, lead time, cost, competitiveness and development prospects for space nuclear power systems (SPS) in the 20 to 200 kWe range. The present three-year study phase is primarily oriented toward the assessment of various reactor candidate technologies and system design options for nuclear SPS in the 20 kWe class, which corresponds to the expected power needs of the first European space missions, anticipated to begin in 2005. This paper presents an overview of the present programme phase, with emphasis on design studies of three reference design concepts for 20 kWe turboelectric nuclear power systems selected so as to cover a wide range of reactor temperatures and corresponding technologies. The systems differ mainly in their nuclear reactors which are: the Liquid Metal Fast Breeder derivative or UO 2 /Na/Stainless steel -650 0 C; the High Temperature Gas-cooled derivative or UO 2 /direct cycle/super alloys - 850 0 C; and the UN/Li/MoRe alloy - 1120 0 C. All three systems use a Brayton cycle with recuperation for power conversion. (author)

  14. 2004 annual report. Defense, safety, energy, information, health. CEA in the center of big European challenges

    International Nuclear Information System (INIS)

    2005-01-01

    This document is the 2004 annual report of the French atomic energy commission (CEA). It presents the R and D activities of the CEA in three main domains: 1 - defense and safety, maintaining perenniality of nuclear dissuasion and nuclear safety: supplying nuclear weapons to armies, maintaining dissuasion capability with the simulation program, sharing R and D means with the scientific community and the industrial world, designing and maintaining naval nuclear propulsion reactors, cleansing Marcoule and Pierrelatte facilities, monitoring treaties and fighting against proliferation and terrorism; 2 - energy, developing more competitive and cleaner energy sources: nuclear waste management, optimization of industrial nuclear activities, future nuclear systems and new energy technologies, basic research on energy, radiobiology and toxicology; 3 - information and health, valorizing industry thanks to technological research and supplying new tools for health and medical research: micro- and nano-technologies, software technologies, basic research for industrial innovation, nuclear technologies for health and bio-technologies. (J.S.)

  15. Simulation of a gas cooled reactor with the system code CATHARE

    International Nuclear Information System (INIS)

    Bentivoglio, Fabrice; Ruby, Alain; Geffraye, Genevieve; Messie, Anne; Saez, Manuel; Tauveron, Nicolas; Widlund, Ola

    2006-01-01

    In recent years the CEA has commissioned a wide range of feasibility studies of future advanced nuclear reactors, in particular gas-cooled reactors (GCR). This paper presents an overview of the use of the thermohydraulics code CATHARE in these activities. Extensively validated and qualified for pressurized water reactors, CATHARE has been adapted to deal also with gas-cooled reactor applications. Rather than branching off a separate GCR version of CATHARE, new features have been integrated as independent options in the standard version of the code, respecting the same stringent procedures for documentation and maintenance. CATHARE has evolved into an efficient tool for GCR applications, with first results in good agreement with existing experimental data and other codes. The paper give an example among the studies already carried out with CATHARE with the case of the Very High Temperature Reactor (VHTR) concepts. Current and future activities for experimental validation of CATHARE for GCR applications are also discussed. Short-term validation activities are also included with the assessment of the German utility Oberhausen II. For the long term, CEA has initiated an ambitious experimental program ranging from small scale loops for physical correlations to component technology and system demonstration loops. (authors)

  16. Influencing factors on the serum carcinoembryonic antigen (CEA) in benign liver diseases

    International Nuclear Information System (INIS)

    Pompecki, R.; Mehl, H.; Fehr, R.; Braun, H. von

    1982-01-01

    Carcinoembryonic antigen (CEA) was determined in the sera of 452 patients with benign liver diseases by radioimmunoassay (CEA-RIA Kit, Abbott). The CEA-level exceeded 2.5 ng/ml in 39 percent and 5.0 ng/ml in 9 percent of the cases. Independent influences of age, nicotin, and alcohol consumption and connective tissue proliferation of the liver on the CEA level were demonstrated and quantified by two- and higher-dimensional contingency table analysis. Toxic liver diseases were combined with elevated serum CEA values more often than inflammatory diseases. This aspect could not be investigated independently since there were only a few cases of toxic liver diseases without alcohol consumption. Sex and relative body weight do not seem to affect the CEA level. Additional diseases of the gastrointestinal tract or the cardiovascular system did not influence the serum CEA level in liver diseases. Therefore, in patients with benign liver diseases, an elevated serum CEA level indicates increased proliferation of the connective tissue. Age, nicotin, and alcohol consumption have to be considered independently in the clinical judgement of elevated serum CEA levels, irrespective of the underlying disease. (orig.) [de

  17. CEA financial report 2007

    International Nuclear Information System (INIS)

    2007-01-01

    This document provides financial data on the CEA for the year 2007. The management report (budget, resources, expenditures) and the accounting are detailed. The main management events of the year 2007 are presented. (A.L.B.)

  18. Education and training in the field of nuclear instrumentation and measurement: CEA/INSTN (National Institute for Nuclear Sciences and Technologies) strategy to improve and develop new pedagogical tools and methods

    Energy Technology Data Exchange (ETDEWEB)

    Vitart, Xavier; Foulon, Francois; Bodineau, Jean Christophe; Lescop, Bernard; Massiot, Philippe [CEA/INSTN Centre des Saclay 91191 Gif sur Yvette (France)

    2015-07-01

    Part of the French Alternative Energies and Atomic Energy Commission (CEA), the National Institute for Nuclear Science and Technology (INSTN) is a higher education institution whose mission is to provide students and professionals a high level of scientific and technological qualification in all disciplines related to nuclear energy applications. In this frame, INSTN carries out education and training (E and T) programs in nuclear instrumentation and radioprotection. Its strategy has always been to complete theoretical courses by training courses and laboratory works carried out on an extensive range of training tools that includes a large panel of nuclear instrumentation as well as software applications. Since its creation in 1956, the INSTN has conducted both education and vocational programs on ionizing radiation detection. An extensive range of techniques have commonly been used during practical works with students and employees of companies who need to get the knowledge and specialization in this field. Today, the INSTN is mainly equipped with usual detectors and electronics in large numbers in order to be able to accommodate up to 48 trainees at the same time in two classrooms, with only two trainees for one workstation in order to optimize their learning. In the field of the neutron detection systems, the INSTN has strongly developed its offer taking advantage of the use of research reactors, such as ISIS reactor (700 kW) at Saclay. The implementation of neutron detection systems specific to the courses offers a unique way of observing and analysing the signal coming from neutron detectors, as well as learning how to set the parameters of the detection system in real conditions. Providing the trainees with an extensive overview of each part of the neutron monitoring instrumentation apply to a nuclear reactor, hands-on measurements on the ISIS reactor play a major role in ensuring a practical and comprehensive understanding of the neutron detection system and

  19. Education and training in the field of nuclear instrumentation and measurement: CEA/INSTN (National Institute for Nuclear Sciences and Technologies) strategy to improve and develop new pedagogical tools and methods

    International Nuclear Information System (INIS)

    Vitart, Xavier; Foulon, Francois; Bodineau, Jean Christophe; Lescop, Bernard; Massiot, Philippe

    2015-01-01

    Part of the French Alternative Energies and Atomic Energy Commission (CEA), the National Institute for Nuclear Science and Technology (INSTN) is a higher education institution whose mission is to provide students and professionals a high level of scientific and technological qualification in all disciplines related to nuclear energy applications. In this frame, INSTN carries out education and training (E and T) programs in nuclear instrumentation and radioprotection. Its strategy has always been to complete theoretical courses by training courses and laboratory works carried out on an extensive range of training tools that includes a large panel of nuclear instrumentation as well as software applications. Since its creation in 1956, the INSTN has conducted both education and vocational programs on ionizing radiation detection. An extensive range of techniques have commonly been used during practical works with students and employees of companies who need to get the knowledge and specialization in this field. Today, the INSTN is mainly equipped with usual detectors and electronics in large numbers in order to be able to accommodate up to 48 trainees at the same time in two classrooms, with only two trainees for one workstation in order to optimize their learning. In the field of the neutron detection systems, the INSTN has strongly developed its offer taking advantage of the use of research reactors, such as ISIS reactor (700 kW) at Saclay. The implementation of neutron detection systems specific to the courses offers a unique way of observing and analysing the signal coming from neutron detectors, as well as learning how to set the parameters of the detection system in real conditions. Providing the trainees with an extensive overview of each part of the neutron monitoring instrumentation apply to a nuclear reactor, hands-on measurements on the ISIS reactor play a major role in ensuring a practical and comprehensive understanding of the neutron detection system and

  20. Deployment of the OSIRIS EM-PIC code on the Intel Knights Landing architecture

    Science.gov (United States)

    Fonseca, Ricardo

    2017-10-01

    Electromagnetic particle-in-cell (EM-PIC) codes such as OSIRIS have found widespread use in modelling the highly nonlinear and kinetic processes that occur in several relevant plasma physics scenarios, ranging from astrophysical settings to high-intensity laser plasma interaction. Being computationally intensive, these codes require large scale HPC systems, and a continuous effort in adapting the algorithm to new hardware and computing paradigms. In this work, we report on our efforts on deploying the OSIRIS code on the new Intel Knights Landing (KNL) architecture. Unlike the previous generation (Knights Corner), these boards are standalone systems, and introduce several new features, include the new AVX-512 instructions and on-package MCDRAM. We will focus on the parallelization and vectorization strategies followed, as well as memory management, and present a detailed performance evaluation of code performance in comparison with the CPU code. This work was partially supported by Fundaçã para a Ciência e Tecnologia (FCT), Portugal, through Grant No. PTDC/FIS-PLA/2940/2014.

  1. Serum carcinoembryonic antigen (CEA) in chronic renal failure

    International Nuclear Information System (INIS)

    Pyo, H.J.; Kim, S.G.; Shin, Y.T.; Kwon, I.S.; Chung, S.I.; Lee, J.S.; Koh, C.S.

    1980-01-01

    The serum CEA levels were measured by radioimmunoassay technique in 15 patients with chronic renal failure, who were not treated with hemodialysis, in 39 patients under hemodialysis and in 23 patients who received renal transplantation. The results were compared with those in 65 normal adults and the following results were obtained. 1) Serum CEA concentrations in 65 normal adults were in the range of 1.0 to 4.3 ng/ml with a mean value of 1.6+-0.66 ng/ml. 2) Serum CEA concentrations in 15 chronic renal failure patients who were not treated with hemodialysis, were in the range of 0.3 to 8.3 ng/ml with a mean value of 3.6+-2.10 ng/ml which was significantly higher than those of normal controls (P 0.05). 4) In 23 patients who received renal transplantation, serum CEA levels were significantly higher than normal controls (P<0.001), but not significantly different from those of chronic renal failure patients. (author)

  2. 2001 overview

    International Nuclear Information System (INIS)

    Anon.

    2002-01-01

    This special issue of 'CEA-Saclay, le Journal' celebrates the 50. anniversary of the very first big facilities (experimental reactors and accelerators) that were put in service at the CEA-Saclay research center. This issue aims at presenting the pluri-disciplinary aspect of the research works that are carried out today at Saclay in the following domains: nuclear energy (Descartes, a new neutronic calculation tool for reactors; a hot laboratory for irradiated materials; a brand new core for Osiris; foreseeing corrosion; cladding under high pressure; how do radionuclide migrate; clay, a barrier to confine nuclear wastes; modeling extreme situations), health (a hope for allergic people; what reading means?; in the heart of brain connections; how the cell organizes its repair?; molecules for cancer targeting; the CEA against mad cow disease), technology (towards the single-electron transistor; toxic ions trapped; neutrons are investigating; a new referential in spectrometry; frequency converting electrons; a new technique to study the porous environments; the Micromegas detector on Ariane's wire; optical fibers for Saint-Jean's bridge; the camera explores Petrus; the French concrete resists well), astrophysics (a fossil in the Milky Way; about the neutrino, only new things; a new eye in the cosmos), climatology/environment (the first secrets of the Vostok lake; the main role of the ocean), physics (does the Earth is doing more than just rotating?; a little nuclear revolution; a step towards the quantum computer; BaBar in search of the lost world; the mysterious kaons), training (tomorrow's energy sources), and documentation (the documentary search at the researchers' service). (J.S.)

  3. Third session: new projects

    International Nuclear Information System (INIS)

    Iracane, D.; Dupuy, J.P.; Perotto, G.; Ithurralde, G.; Cabrillat, J.C.; Becle, D.; Pivet, S.; Minguet, J.L.

    2005-01-01

    The RJH (Jules Horowitz reactor) is a 100 MWth research reactor, cooled and moderated by water, that has been designed to operate with high density (8 g U/cm 3 ) and low enrichment fuel (19.75%) uranium molybdenum fuel. Its main neutron performances are expected to be: -) maximum fast neutron flux (E > 0.907 MeV) in the sample: 5.10 14 n/cm 2 /s, -) maximum thermal neutron flux (E 14 n/cm 2 /s, and -) maximal neutron damage: 16 dpa/year. RJH that will be built on the Cea's site of Cadarache, is scheduled to enter into service in 2014, it will take over the activities of the Osiris reactor and its operating life is planned to be over 50 years long. The Cabri research reactor is located on the Cadarache site, it has been operating since 1962 and is now undergoing important upgrading operations whose aim is to make the facility fit to study the behaviour of new nuclear fuels in accidental situations. The RES test reactor is a facility whose aim is to qualify nuclear fuels and core configurations of existing propulsion reactors onboard of aircraft carriers or submarines and to propose innovative concepts for future propulsion reactors. (A.C.)

  4. Progress Report 1994

    International Nuclear Information System (INIS)

    1995-01-01

    This document is the 1994 annual progress report of the CEA-Direction of Waste Management (DGD). It comprises four chapters. The first chapter is a general presentation of radioactive wastes, of the management of liquid effluents, solid wastes, sealed sources, of the relations with the ANDRA (The French Agency for the Management of Radioactive Wastes), and of the research and development studies in progress for the improvement of waste management. The second chapter concerns the spent fuels and their reprocessing, in particular AGR and PWR type reactor fuels, the ''Caramel'' fuel from Osiris reactor and the cover elements from the Rapsodie reactor core. The long time storage of ancient fuels is also discussed. The third chapter concerns the dismantling of decommissioned installations, the actions in progress and the planning of dismantling actions up to the year 2000. Chapter four is devoted to the management of wastes from the Direction of Military Applications (DAM), the actions in progress in the different DAM centers and the cleansing projects at Marcoule plant. (J.S.). 5 figs., 28 tabs., 21 photos., 3 appendix

  5. Progress Report 1994; Rapport d`activite 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    This document is the 1994 annual progress report of the CEA-Direction of Waste Management (DGD). It comprises four chapters. The first chapter is a general presentation of radioactive wastes, of the management of liquid effluents, solid wastes, sealed sources, of the relations with the ANDRA (The French Agency for the Management of Radioactive Wastes), and of the research and development studies in progress for the improvement of waste management. The second chapter concerns the spent fuels and their reprocessing, in particular AGR and PWR type reactor fuels, the ``Caramel`` fuel from Osiris reactor and the cover elements from the Rapsodie reactor core. The long time storage of ancient fuels is also discussed. The third chapter concerns the dismantling of decommissioned installations, the actions in progress and the planning of dismantling actions up to the year 2000. Chapter four is devoted to the management of wastes from the Direction of Military Applications (DAM), the actions in progress in the different DAM centers and the cleansing projects at Marcoule plant. (J.S.). 5 figs., 28 tabs., 21 photos., 3 appendix.

  6. A stratospheric NO2 climatology from Odin/OSIRIS limb-scatter measurements

    International Nuclear Information System (INIS)

    Brohede, S.; Murtagh, D.; Berthet, G.; Haley, C.S.

    2007-01-01

    Since the late 1960s, it has been known that stratospheric nitrogen dioxide (NO 2 ) and ozone are closely coupled. However, stratospheric nitrogen chemistry is not yet fully understood, given the lack of observing systems that can provide both high vertical and temporal resolution measurements of NO 2 . Limb-scattering data from the optical spectrograph and infrared imager system (OSIRIS) aboard the Odin satellite was used in this study along with a photochemical box model to investigate stratospheric NO 2 climatology in terms of mean and standard deviation as a function of latitude, altitude, month and local solar time. The Odin orbit provided near global coverage around the equinoxes and hemispheric coverage elsewhere, due to lack of sunlight. The mean NO 2 field at a specific local solar time involved high concentrations in the polar summer, peaking at about 25 km, with a negative equatorward gradient. High levels between 40 to 50 degrees latitude at 30 km in the winter/spring hemisphere were also found, and were associated with the Noxon-cliff. The diurnal cycle revealed the lowest NO 2 concentrations just after sunrise and steep gradients at twilight. The 1σ standard deviation was around 20 per cent, except for winter and spring high latitudes, where values were above 50 per cent and stretched through the entire stratosphere. NO 2 concentrations were found to be log-normally distributed. Comparisons with the REPROBUS chemical transport model for climatology showed that the relative differences for the mean values were below 20 per cent and comparable to the estimated OSIRIS systematic uncertainty. The polar regions in winter/spring throughout the atmosphere and equatorial regions below 25 km were exceptions, where OSIRIS was higher by 40 per cent and more. It was concluded that further study is needed to determine if these discrepancies are due to limitations of the model. 47 refs., 10 figs., 1 appendix

  7. Hearing of Mr Bernard Bigot, general administrator of the Atomic Energy Commissariat (CEA), on the CEA missions and on Cadarache events

    International Nuclear Information System (INIS)

    2009-01-01

    In this hearing by the Sustainable Development and Land Planning Commission of the French National Assembly, the role and missions of the CEA are presented while evoking its relationship with the State. The CEA representative evokes the various research activities in three main domains: energy, defence, information and health technologies. Then, he discusses the problem of the ageing and dismantling of some installations, notably in the plutonium Technology workshop (ATPu) in Cadarache. He describes this installation, the processes in which it is involved, the safety and security requirements, and comments the problem which occurred in this workshop (plutonium retention in glove boxes). Then he answers several questions asked by the Commission members about the way the CEA handled this incident, and about its severity. Other aspects are addressed like the importance of the nuclear industry and the role the CEA could have in the management of renewable energies at the national level

  8. CEA and mining industry

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    The French atomic energy commission (CEA) is involved in the mining industry in several ways: - in the front-end of the nuclear industry through its daughter companies and participations in the exploration and exploitation of uranium ores, but also of gold and alloy metals with a 26% participation in Eramet company, the world leader of manganese and nickel. This activity is the main occupation of Cogema daughter company, via the Areva holding; - in the back-end of the nuclear fuel cycle with the delicate problem of the management of radioactive wastes; - in parallel with the nuclear industry through an important activity in semiconductor materials (FCI and SMTElectronics); - and finally through various research works on several mineral compounds. This article focusses on the fuel cycle aspects of the CEA activities and concludes with the research works carried out today on thermonuclear fusion. (J.S.)

  9. Anti-CEA loaded maghemite nanoparticles as a theragnostic device for colorectal cancer

    Directory of Open Access Journals (Sweden)

    Campos da Paz M

    2012-10-01

    Full Text Available Mariana Campos da Paz,1 Maria de Fátima M Almeida Santos,1 Camila MB Santos,2 Sebastião W da Silva,2 Lincoln Bernardo de Souza,3 Emília CD Lima,3 Renata C Silva,1 Carolina M Lucci,1 Paulo César Morais,2 Ricardo B Azevedo,1 Zulmira GM Lacava11Instituto de Ciências Biológicas; 2Instituto de Física, Universidade de Brasília, Brasília, DF, Brazil; 3Instituto de Química, Universidade Federal de Goiás, Goiânia, GO, BrazilAbstract: Nanosized maghemite particles were synthesized, precoated (with dimercaptosuccinic acid and surface-functionalized with anticarcinoembryonic antigen (anti-CEA and successfully used to target cell lines expressing the CEA, characteristic of colorectal cancer (CRC cells. The as-developed nanosized material device, consisting of surface decorated maghemite nanoparticles suspended as a biocompatible magnetic fluid (MF sample, labeled MF-anti-CEA, was characterized and tested against two cell lines: a high-CEA expressing cell line (LS174T and a low-CEA expressing cell line (HCT116. Whereas X-ray diffraction was used to assess the average core size of the as-synthesized maghemite particles (average 8.3 nm in diameter, dynamic light scattering and electrophoretic mobility measurements were used to obtain the average hydrodynamic diameter (550 nm and the zeta-potential (−38 mV of the as-prepared and maghemite-based nanosized device, respectively. Additionally, surface-enhanced Raman spectroscopy (SERS was used to track the surface decoration of the nanosized maghemite particles from the very first precoating up to the attachment of the anti-CEA moiety. The Raman peak at 1655 cm−1, absent in the free anti-CEA spectrum, is the signature of the anti-CEA binding onto the precoated magnetic nanoparticles. Whereas MTT assay was used to confirm the low cell toxicity of the MF-anti-CEA device, ELISA and Prussian blue iron staining tests performed with both cell lines (LS174T and HCT116 confirm that the as-prepared MF-anti-CEA

  10. Comparison of CA15-3 and CEA in breast cancer

    International Nuclear Information System (INIS)

    Rajkovaca, Z.; Mijatovic, J.; Matavulj, A.; Kovacevic, P.; Ponorac, N.

    2002-01-01

    Aim: Tumor markers are potentially powerful means for obtaining information about cancers whilst causing minimal morbidity, inconvenience and cost. CA 15-3 and CEA are considered useful tumor markers in monitoring breast cancer patients. The aim of this study was to evaluate which of these two markers are in better correlate with the disease in patients surgically treated for breast cancer. Material and Methods: We retrospectively reviewed values of CA15-3 and CEA in 342 patients (median age 52.18 years, range 27-78 years) with surgically treated and pathologically proven breast cancer. CA15-3 and CEA was measured by radioimmunoassay. CA15-3 levels above 30 U/ml and CEA levels above 5 ng/ml were considered as positive values. Results: Out of 342 patients, 86 had elevated CA15-3 levels (sensitivity: 25.1%) and 68 of 342 patients had positive CEA levels (sensitivity 19.9%). Two hundred thirty seven (237) of the patients suffering from breast cancer (69.3%) did not have metastatic disease. In this group CA15-3 sensitivity was 94.5%, while CEA sensitivity was 87.3%. One hundred and five (105) patients (30.7%) had metastatic disease. In this group, CA15-3 sensitivity was 69.5% and CEA sensitivity was 36.2% (P < 0.05). With regard to the correlation of the two tumor markers with clinical course patients had significantly higher levels of CA15-3 than of CEA in metastatic breast cancer. Conclusion: This result suggests CA15-3 to be the more sensitive and more specific of the two tumor markers for metastatic breast cancer detection and monitoring

  11. International collaborations about fuel studies for reactor recycling of military quality plutonium

    International Nuclear Information System (INIS)

    Bernard, H.; Chaudat, J.P.

    1997-01-01

    In November 1992, an agreement was signed between the French and Russian governments to use in Russia and for pacific purposes the plutonium recovered from the Russian nuclear weapons dismantling. This plutonium will be transformed into mixed oxide fuels (MOX) for nuclear power production. The French Direction of Military Applications (DAM) of the CEA is the operator of the French-Russian AIDA program. The CEA Direction of Fuel Cycle (DCC) and Direction of Nuclear Reactors (DRN) are involved in the transformation of metallic plutonium into sinterable oxide powder for MOX fuel manufacturing. The Russian TOMOX (Treatment of MOX powder Metallic Objects) and DEMOX (MOX Demonstration) plants will produce the MOX fuel assemblies for the 4 VVER 1000 reactors of Balakovo and the fast BN 600 reactor. The second part of the program will involve the German Siemens and GRS companies for the safety studies of the reactors and fuel cycle plants. The paper gives also a brief analysis of the US policy concerning the military plutonium recycling. (J.S.)

  12. In vitro and in vivo comparison of binding of 99m-Tc-labeled anti-CEA MAb F33-104 with 99m-Tc-labeled anti-CEA MAb BW431/26

    International Nuclear Information System (INIS)

    Watanabe, N.; Gunma Univ. School of Medicine; Oriuchi, N.; Inoue, T.; Sugiyama, S.; Kuroki, M.; Matsuoka, Y.; Tanada, S.; Murata, H.; Sasaki, Y.

    1999-01-01

    Aim: The purpose of this study was to assess the potential for radioimmunodetection (RAID) of murine anti-carcinoembryonic antigen (CEA) monoclonal antibody (MAb) F33-104 labeled with technetium-99m (99m-Tc) by a reduction-mediated labeling method. Methods: The binding capacity of 99m-Tc-labeled anti-CEA MAb F33-104 with CEA by means of in vitro procedures such as immunoradiometric assay and cell binding assay and the biodistribution of 99m-Tc-labeled anti-CEA MAb F33-104 in normal nude mice and nude mice bearing human colon adenocarcinoma LS180 tumor were investigated and compared with 99m-Tc-labeled anti-CEA MAb BW431/26. Results: The in vitro binding rate of 99m-Tc-labeled anti-CEA MAb F33-104 with CEA in solution and attached to the cell membrane was significantly higher than 99m-Tc-labeled anti-CEA MAb BW431/261 (31.4 ± 0.95% vs. 11.9 ± 0.55% at 100 ng/mL of soluble CEA, 83.5 ± 2.84% vs. 54.0 ± 2.54% at 10 7 of LS 180 cells). In vivo, accumulation of 99m-Tc-labeled anti-CEA MAb F33-104 was higher at 18 h postinjection than 99m-Tc-labeled anti-CEA MAb BW431/26 (20.1 ± 3.50% ID/g vs. 14.4 ± 3.30% ID/g). 99m-Tc-activity in the kidneys of nude mice bearing tumor was higher at 18 h postinjection than at 3 h (12.8 ± 2.10% ID/g vs. 8.01 ± 2.40% ID/g of 99m-Tc-labeled anti-CEA MAb F33-104, 10.7 ± 1.70% ID/g vs. 8.10 ± 1.75% ID/g of 99m-Tc-labeled anti-CEA MAb BW431/26). Conclusion: 99m-Tc-labeled anti-CEA MAb F33-104 is a potential novel agent for RAID of recurrent colorectal cancer. (orig.) [de

  13. The CEA in mutation redefines its strategy

    International Nuclear Information System (INIS)

    Anon.

    2005-01-01

    The French atomic energy commission has redefined its medium- and long-term plan which fixes its strategy for the ten coming years. A. Bugat, general director of the CEA briefly presents the new missions of the CEA: budget and investments, cooperation with universities, place of fundamental research, activities in fuel cells and photovoltaic energy, cooperation with EdF, Areva and Cogema in civil nuclear research. Short paper. (J.S.)

  14. Carcinoembryonic antigen (CEA) dynamics in stomach cancer patients receiving cryotherapy

    International Nuclear Information System (INIS)

    Myasoedov, D.V.; Krupka, I.N.; V'yunitskaya, L.V.

    1986-01-01

    Radioimmunologic assays of blood serum carcinoembryonic antigen (CEA) level were conducted at major stages of treatment of gastric cancer by subtotal stomach resection and gastrectomy with preliminary cryotreatment and thawing of tumor. A short-term rise in CEA level occurred in 53.9 % of cases 3-4 days after combined therapy. A decrease in CEA concentration at discharge from hospital as compared with preoperative level and that registered 3-4 days after operation was observed in 50 and 75 % of cases of combined therapy, respectively, and 47.5 and 37.5 % of controls (surgery without cryotreatment). There was nocorrelation between cryotreatment and changes in CEA level in gastric ulcer patients

  15. Preliminary study of a flux converter for experimental reactor

    International Nuclear Information System (INIS)

    Malouch, M.F.

    1998-01-01

    The purpose of this project is to define the characteristics of a flux converter dedicated to increase the fast neutron flux in irradiation devices placed in the core of Osiris experimental reactor. This preliminary work has dealt with the neutronic and thermal-hydraulic aspects of this problem. The synthesis of the results produced by the codes APOLLO2, DAIXY, MERCURE5.3 and FLICA-3M shows that a cylindrical converter equipped with 5 fissile rings can enhance the fast flux by a 35% factor in an experimental device set in its center. (A.C.)

  16. INIS, CEA and nuclear terminology

    International Nuclear Information System (INIS)

    Surmont, J.; Brulet, C.; Constant, A.; Guille, N.; Le Blanc, A.; Mouffron, O.; Anguise, P.; Jouve, J.J.

    2007-01-01

    This poster, prepared for the fifth edition of the meetings of scientific and technical information professionals (RPIST, Nancy (France)), presents, first, the INIS information system, its content and coverage, the French participation to this system and the role of the CEA-Saclay as France's official representative for this system. Then it presents the INIS thesaurus with its different levels as a terminological tool for the indexing of documents and for searching documents inside the database. Finally, the very first electronic version of the multilingual thesaurus is introduced. Several national INIS centres, including the CEA-Saclay, have contributed to the translation of lists of new terms and of forbidden terms (synonyms). (J.S.)

  17. A study of factors influencing plasma CEA levels in an unselected population.

    Science.gov (United States)

    Herbeth, B; Bagrel, A

    1980-01-01

    Plasma carcinoembryonic antigen (CEA) levels were measured by an immunoenzymic method (Abbott) in 1020 subjects attending the Preventive Medicine Centre (Vandoeuvre-les-Nancy). The results are assessed in relation to: sex, age, body build, fasting/normal food intake, smoking, alcohol intake, drug medication, and working environment. The mean plasma CEA level is 1.53 ng/ml. 87% of the total group has levels less than 2.5 ng/ml, 11.2% levels between 2.5 ng/ml and 5 ng/ml and 1.8% levels above 5 ng/ml. One person had a level above 10 ng/ml. Men had significantly higher CEA levels than women. Smoking was more frequent in both men and women with CEA levels above 2.5 ng/ml. Only in men were age, alcohol consumption and a poor work environment significantly associated with CEA levels higher than 2.5 ng/ml. Obesity in women was related to higher CEA levels. Food intake and drug medication were without influence on the CEA level.

  18. Nuclear systems of the future: international forum generation 4 and research and development projects at the Cea

    International Nuclear Information System (INIS)

    Carre, F.

    2003-01-01

    To advance nuclear energy to meet future energy needs, ten countries have agreed to develop a future generation of nuclear energy systems, known as Generation 4. A technology road map to guide the Generation 4 effort was begun. This document presents the goals for these nuclear systems and the research programs of the Cea on the gas technology, GT-MHR, VHTR and GFR and the other systems as sodium Fast Neutron reactors, supercritical water and space nuclear. (A.L.B.)

  19. Introduction to the CEA family: structure, function and secretion.

    Science.gov (United States)

    Von Kleist, S

    1992-01-01

    Due to the phenomenal progress in the field of tumor immunology that took place during the last twenty years, we dispose today of highly specific and sensitive techniques and reagents like monoclonal antibodies (MAbs). In this context the discovery in human carcinomas of tumor-associated antigens, such as CEA, was of primary importance, especially since the latter was found to have clinical relevance as a tumor marker. Based on animal models, a new in vivo technology for the detection of tumors and metastases was developed in recent years, that uses anti-CEA MAbs, or fragments of them, coupled to radio-isotopes. This technique, called radio-immunodetection (RAID), also paved the way for immunotherapeutic procedures, where again CEA served as the target-antigen. This new technique holds great promise, provided the epitope-specificity of the MAbs is well-controlled: it has been shown that CEA belongs to a large gene-family of at least 22 members, which can be subdivided into two subgroups (i.e., the CEA- and the PSG-subgroup) and which in turn belongs to the immunoglobulin-supergene family. Great structural similarities render the distinction of the various cross-reactive molecules by immunological means rather difficult.

  20. Use of OsiriX in developing a digital radiology teaching library.

    Science.gov (United States)

    Shamshuddin, S; Matthews, H R

    2014-10-01

    Widespread adoption of digital imaging in clinical practice and for the image-based examinations of the Royal College of Radiologists has created a desire to provide a digital radiology teaching library in many hospital departments around the UK. This article describes our experience of using OsiriX software in developing digital radiology teaching libraries. Copyright © 2014 The Royal College of Radiologists. Published by Elsevier Ltd. All rights reserved.

  1. Opening the terahertz window on the OSIRIS spectrometer

    Directory of Open Access Journals (Sweden)

    Demmel F.

    2015-01-01

    Full Text Available A cooled and mechanically retractable beryllium filter has been installed and commissioned on the low-energy OSIRIS spectrometer at ISIS. This instrument development extends the energy-transfer range of the spectrometer up to ca. 20 meV (∼ 5 THz, leading to an excellent resolution at THz frequencies and substantial gains in detected flux relative to existing capabilities on the neighbouring IRIS spectrometer. Herein, we provide a concise account of this new capability for high-resolution neutron spectroscopy in the THz domain, as well as outline a number of ongoing and potential scientific opportunities in condensed-matter physics, chemistry, and materials science.

  2. The organisation of criticality hazard prevention at the CEA

    International Nuclear Information System (INIS)

    Mijuin, Dominique; Carros, Helene; Sevestre, Bernard

    2003-01-01

    This paper deals with the organisation of criticality hazard prevention at the French Atomic Energy Commission (CEA). This new organization has been experimented since the end of year 2000. During the first semester of year 2002, the CEA nuclear inspection team, who is in charge of the control function at the CEA general administration level, has performed an inquiry to check the effectiveness of the new organization. The conclusions of this inquiry are very positive; a few recommendations are now taken in to account to further improve the efficiency of this organization. (J.P.N.)

  3. CEA - Assessment of risk management for 2012

    International Nuclear Information System (INIS)

    Bonnevie, Edwige

    2013-06-01

    This report proposes an overview of the main events, actions performed by the CEA, and facts for 2012 regarding protection and monitoring of the environment, installation safety, occupational health and safety, radiological protection of workers, transportation of hazardous materials, waste management, protection of sites, installations and heritage, emergency situation management, legal risk management, internal controls and audits. It also presents the organisation and action of the risk management department within the CEA

  4. CEA 2009 annual report

    International Nuclear Information System (INIS)

    2010-01-01

    After an indication of several key figures about the activity of the CEA (Centre d'Etudes Atomiques) and its relationship with the academic as well as the industrial field, in France and worldwide, this 2009 annual report presents its various research programs in the field of defence and of global security: basic research (nuclear weapons and propulsion, struggle against proliferation and terrorism) and applied research (nuclear deterrence, national and international security). Then, it presents the programs in the field of de-carbonated energy: basic research (in material science and in life sciences) and applied research (fission energy, fusion energy, new energy technologies). A last group of research programs deals with information and health technologies and concerns life and material sciences, micro- and nano-technologies, software technologies. Interaction with other research institutions and bodies is also evoked. A brief scientific assessment is proposed. Finally, the different structures building the CEA are presented

  5. Tumor, serum and urine carcinoembryonic antigen (CEA) in upper urinary tract urothelial cancer

    International Nuclear Information System (INIS)

    Stefanovic, V.; Ignjatovic, M.

    1987-01-01

    The aim of this investigation was to study the possible diagnostic value of a CEA test in cancer of the renal pelvis and ureter. Thirty-eight patients with upper urinary tract cancer, 15 patients with transitional cell carcinoma of the bladder, 6 kidney carcinoma patients and 25 healthy adults were studied. CEA was determined in tumor tissue, serum and urine, by using a monoclonal radioimmunoassay. Increased serum CEA level was found in 7 out of 27 patients (26%) with active cancer of the renal pelvis and ureter. None of 11 patients with inactive cancer had an increased serum CEA level. No significant correlation was found between the serum CEA level and the histological grading. The tumor CEA content varied markedly, from values obtainted in normal urothelium up to 840 ng/g wet weight. CEA content of tumor tissue did not correlate with the serum level. Our data suggest that serum and urine CEA have not diagnostic accuracy for clinical diagnosis of upper tract urothelial cancer. (orig.) [de

  6. Clinical investigation of serum CEA in 120 patients with colorectal cancer

    International Nuclear Information System (INIS)

    Li Yusheng; Yang Liting; Yu Yunyun; Yu Suqing; Ma Shuqin

    2003-01-01

    To investigate the correlation between serum CEA and colorectal cancer, the pre-and postoperative serum CEA in 120 patients with colorectal cancer was measured by RIA, with other 24 cases of healthy donors as control. The results showed that serum CEA in control group and patient group were 9.84±2.44 ng/mL, 38, 85±19.21 ng/mL respectively, while colonic cancer group 37.43±18.58 ng/mL, rectal cancer group 39.72±20.67 ng/mL. There was significant difference between patient group and control group (P 0.05). Serum CEA of 37 among 44 cases with positive CEA findings decreased to 11.21±3.65 ng/mL during two months follow-up post-operation, whereas 50.63±24.38 ng/mL in 7/44 cases undergoing non-radical operation. The serum CEA of 41 recurrence cases was 43.12±17.15 ng/mL at six-year post-operation, with 87.80% of three-year recurrence rate. It suggested that the serum CEA test is a convenient method for colorectal cancer to preoperatively diagnose it, evaluate postoperative curative effect and detect tumor recurrence and metastasis

  7. Status of the French research in the field of molten salt nuclear reactors

    International Nuclear Information System (INIS)

    Hery, M.; Israel, M.; Fauger, P.; Lecocq, A.

    1977-01-01

    The research program of the CEA in the field of molten salt nuclear reactors has been concerned with MSBR type reactors (Molten Salt Breeder Reactor). The papers written after having performed the theoretical analysis are entitled: core, circuits, chemistry and economy; they include some criticisms and suggestions. The experimental studies consisted in: graphite studies, chemical studies of the salt, metallic materials, the salt loop and the lead loop [fr

  8. The opening of the CEA to the general public

    International Nuclear Information System (INIS)

    Deloche, Robert

    1999-01-01

    Full text: The relationships between science and society have evolved considerably over the past years, just like the perception of the nuclear industry in the French public opinion. Recent psychosociological surveys show that only half of the French population is familiar with the CEA and that the public would like to obtain new elements of judgment in order to be able to develop a direct appreciation of the activities of a research organization such as the Atomic Energy Commission. It is essential to meet the public's expectations, to keep it properly informed of the CEA's research activities, and to help it understand the relevance of the results obtained and the solutions offered to decision-makers, i.e. industrialists and public authorities. One way to answer the public opinion's questions and to meet its expectations is to allow a rowing number of visitors to see who we are, what we study in our laboratories, and how we work to contribute to scientific progress and to the diffusion of technology, in a manner that is useful to society as a whole. This describes the spirit and the objective that governed the very idea and elaboration of the program entitled 'Opening of the CEA to the general public'. This operation consists not only in having communication specialists guide visitors throughout the facilities and equipment of the CEA, but also in encouraging researchers and groups of visitors to meet in the laboratories. A 'CEA - communication' network is under construction. It already has nearly 600 members. Communication is considered to be a real calling that falls within the scope of the CEA's strategy, and the work accomplished in this respect is recognized to the same extent as research. To this end, a charter for the CEA - communication network will be signed by every contributor and manager. A training scheme focused on public speaking and scientific vulgarization was initiated. 50 members of the network have already been trained, and 250 will be in 1999

  9. In vivo localization of radiolabeled monoclonal antibody to carcinoembryonic antigen (CEA) in a CEA-producing tumor

    International Nuclear Information System (INIS)

    Kamei, Tetsuya; Seto, Hikaru; Taki, Kuniyasu; Soya, Toshio; Kakishita, Masao; Maeda, Masatoshi; Honda, Takashi; Koshimura, Saburou.

    1987-01-01

    To compare accumulation of the 125 I-labeled antibodies(anti-carcinoembryonic antigen(CEA) monoclonal antibody and polyclonal antibody) to a CEA-producing tumor (SC-2-JCK), an in vivo localization study was performed in nude mice. The tumor-to-blood ratio at 120 hours after injection rose to 4.6 for the monoclonal antibody, but remained at 1.3 for the polyclonal antibody. However, no differences were noted between the antibodies up to 72 hours after injection. In autoradiograms, selective accumulation of the tracer was noted in the tumor for both antibodies. However, no superiority or inferiority of imaging for either of the antibodies could be definitely determined. (author)

  10. Osiris wrapped with the skin of the celestial fawn: note on D. S. I 11.4

    Directory of Open Access Journals (Sweden)

    Jónatan Ortiz-García

    2017-09-01

    Full Text Available In this paper it is proposed an explanation for certain information transmitted by Diodorus Siculus, according to which the Egyptian god Osiris was wrapped with a fawn skin with stars.

  11. Caramel, uranium oxide fuel plates for water cooled reactors

    International Nuclear Information System (INIS)

    Bussy, Pierre; Delafosse, Jacques; Lestiboudois, Guy; Cerles, J.-M.; Schwartz, J.-P.

    1979-01-01

    The fuel is composed of thin plates assembled parallel to each other to form bundles or assemblies. Each plate is composed of a pavement of uranium oxide pellets, insulated from each other by a zircaloy cladding. The 235 U enrichment does not exceed 8%. The range of uses for this fuel extends from electric power generating reactors to irradiation reactors for research work. A parametric study in test loops has made it possible to determine the operating limits of this thick fuel, without bursting. The resulting diagram gives the permissible power densities, with and without cycling for specific burn-ups beyond 50,000 MWd/t. The thinnest plates were also irradiated in total in the form of advance assemblies irradiated in the core of the OSIRIS pile prior to its transformation. This transformation and the operation of this reactor with a core of 'Caramel' elements is the main trial experiment of this fuel [fr

  12. Revised Correlation between Odin/OSIRIS PMC Properties and Coincident TIMED/SABER Mesospheric Temperatures

    Science.gov (United States)

    Feofilov, A. G.; Petelina, S. V.; Kutepov, A. A.; Pesnell, W. D.; Goldberg, R. A.; Llewellyn, E. J.; Russell, J. M.

    2006-01-01

    The Optical Spectrograph and Infrared Imaging System (OSIRIS) instrument on board the Odin satellite detects Polar Mesospheric Clouds (PMCs) through the enhancement in the limb-scattered solar radiance. The Sounding of the Atmosphere using the Broadband Emission Radiometry (SABER) instrument on board the TIMED satellite is a limb scanning infrared radiometer that measures temperature and vertical profiles and energetic parameters for minor constituents in the mesosphere and lower thermosphere. The combination of OSIRIS and SABER data has been previously used to statistically derive thermal conditions for PMC existence [Petelina et al., 2005]. a, A.A. Kutepov, W.D. Pesnell, In this work, we employ the simultaneous common volume measurements of PMCs by OSIRIS and temperature profiles measured by SABER for the Northern Hemisphere summers of 2002-2005 and corrected in the polar region by accounting for the vibrational-vibrational energy exchange among the CO2 isotopes [Kutepov et al., 2006]. For each of 20 coincidences identified within plus or minus 1 degree latitude, plus or minus 2 degrees longitude and less than 1 hour time the frost point temperatures were calculated using the corresponding SABER temperature profile and water vapor densities of 1,3, and 10 ppmv. We found that the PMC presence and brightness correlated only with the temperature threshold that corresponds to the frost point. The absolute value of the temperature below the frost point, however, didn't play a significant role in the intensity of PMC signal for the majority of selected coincidences. The presence of several bright clouds at temperatures above the frost point is obviously related to the limitation of the limb geometry when some near- or far-field PMCs located at higher (and warmer) altitudes appear to be at lower altitudes.

  13. Effect of volcanic aerosol on stratospheric NO2 and N2O5 from 2002–2014 as measured by Odin-OSIRIS and Envisat-MIPAS

    Directory of Open Access Journals (Sweden)

    C. Adams

    2017-07-01

    Full Text Available Following the large volcanic eruptions of Pinatubo in 1991 and El Chichón in 1982, decreases in stratospheric NO2 associated with enhanced aerosol were observed. The Optical Spectrograph and Infrared Imaging Spectrometer (OSIRIS measured the widespread enhancements of stratospheric aerosol following seven volcanic eruptions between 2002 and 2014, although the magnitudes of these eruptions were all much smaller than the Pinatubo and El Chichón eruptions. In order to isolate and quantify the relationship between volcanic aerosol and NO2, NO2 anomalies were calculated using measurements from OSIRIS and the Michelson Interferometer for Passive Atmospheric Sounding (MIPAS. In the tropics, variability due to the quasi-biennial oscillation was subtracted from the time series. OSIRIS profile measurements indicate that the strongest anticorrelations between NO2 and volcanic aerosol extinction were for the 5 km layer starting  ∼  3 km above the climatological mean tropopause at the given latitude. OSIRIS stratospheric NO2 partial columns in this layer were found to be smaller than background NO2 levels during these aerosol enhancements by up to  ∼  60 % with typical Pearson correlation coefficients of R ∼ −0. 7. MIPAS also observed decreases in NO2 partial columns during periods affected by volcanic aerosol, with percent differences of up to  ∼  25 % relative to background levels. An even stronger anticorrelation was observed between OSIRIS aerosol optical depth and MIPAS N2O5 partial columns, with R ∼ −0. 9, although no link with MIPAS HNO3 was observed. The variation in OSIRIS NO2 with increasing aerosol was found to be consistent with simulations from a photochemical box model within the estimated model uncertainty.

  14. Distance determination method of dust particles using Rosetta OSIRIS NAC and WAC data

    Science.gov (United States)

    Drolshagen, E.; Ott, T.; Koschny, D.; Güttler, C.; Tubiana, C.; Agarwal, J.; Sierks, H.; Barbieri, C.; Lamy, P. I.; Rodrigo, R.; Rickman, H.; A'Hearn, M. F.; Barucci, M. A.; Bertaux, J.-L.; Bertini, I.; Cremonese, G.; da Deppo, V.; Davidsson, B.; Debei, S.; de Cecco, M.; Deller, J.; Feller, C.; Fornasier, S.; Fulle, M.; Gicquel, A.; Groussin, O.; Gutiérrez, P. J.; Hofmann, M.; Hviid, S. F.; Ip, W.-H.; Jorda, L.; Keller, H. U.; Knollenberg, J.; Kramm, J. R.; Kührt, E.; Küppers, M.; Lara, L. M.; Lazzarin, M.; Lopez Moreno, J. J.; Marzari, F.; Naletto, G.; Oklay, N.; Shi, X.; Thomas, N.; Poppe, B.

    2017-09-01

    The ESA Rosetta spacecraft has been tracking its target, the Jupiter-family comet 67P/Churyumov-Gerasimenko, in close vicinity for over two years. It hosts the OSIRIS instruments: the Optical, Spectroscopic, and Infrared Remote Imaging System composed of two cameras, see e.g. Keller et al. (2007). In some imaging sequences dedicated to observe dust particles in the comet's coma, the two cameras took images at the same time. The aim of this work is to use these simultaneous double camera observations to calculate the dust particles' distance to the spacecraft. As the two cameras are mounted on the spacecraft with an offset of 70 cm, the distance of particles observed by both cameras can be determined by a shift of the particles' apparent trails on the images. This paper presents first results of the ongoing work, introducing the distance determination method for the OSIRIS instrument and the analysis of an example particle. We note that this method works for particles in the range of about 500-6000 m from the spacecraft.

  15. The 'Reacteur Jules Horowitz': a new experimental reactor project

    International Nuclear Information System (INIS)

    Frachet, S.; Ballagny, A.

    1999-01-01

    The Jules Horowitz Reactor (RJH) is a new research reactor project dedicated to materials and nuclear fuel testing, the location of which is foreseen at the CEA-CADARACHE site, and the start-up in 2006. The launching of this project originated from a double finding: The development of nuclear power plants aimed at satisfying the energy needs of the next century, cannot be envisaged without experimental reactors which are unrivaled for the validation of new concepts of nuclear fuels, materials, and components as well as for their qualification under irradiation. The existing experimental reactors are 30 to 40 years old and it is advisable to examine henceforth the necessity for and the nature of a new reactor to take over and replace, at the beginning of next century, the reactors shut-down in the mean time or at the very end of their lives. Within this framework, the CEA has undertaken, in the last years, a study on the mid and long term irradiation needs, to determine the main features and performances of this new reactor. The concept of the reactor will have to fulfill the thermal neutron irradiation requirements as well as the fast neutron experimental needs, with a great potential versatility for any new irradiation programs. The reactor project selected among several different concepts, is finally a light water pool concept, with 100 MW thermal power. It could reach neutronic fluxes twice those of present French reactors, and allows for many irradiations in and around the core, under high neutron fluxes. The reactor will satisfy the highest level of safety in full accordance with international safety recommendations and the French safety approach for this kind of nuclear facility, thus giving an added safety margin keeping in mind the versatility of research reactors. The feasibility studies have been focused on the following most important items: neutronic and thermalhydraulic studies on alternative core designs, with or without added pressurization

  16. Osiris: an object oriented software tool for modelling the logistics, economics and environmental impact of the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Millington, D.N.

    2003-01-01

    Osiris is a general purpose software tool which has been developed for performing studies of material usage, economics and environmental impacts associated with the nuclear fuel cycle. It is particularly suited to the analysis of complex multiple recycling scenarios featuring combinations of both existing and new reactor systems. A discrete event model is used to represent the movement of material batches around the fuel cycle due to the operations and timings of process plants. Nuclear materials are represented by state vectors, which undergo compositional changes due to radioactive decay and irradiation. A library of generic plant types is provided, which are declared and configured in order to represent specific plants. Reactors, front-end and back-end process plants, buffers, stores and material sources can be modelled. Fuel cycle scenarios are then constructed by defining the material flow paths between the plants. The plant parameters and flow paths can be altered dynamically over the course of a scenario in order to represent changes in recycling strategies and retirement and replacement of process plants. Discounted electricity costs can be determined by assigning unit costs to all capital investments, processes and raw materials. Radiotoxicity levels of waste streams can also be evaluated. The software was developed in C++ using objected oriented analysis and design methods. The use of abstraction and inheritance have enabled an open-ended fuel cycle modelling environment to be established, into which new reactor or plant models can readily be integrated. An overview of the object model, numerical modelling assumptions and the design and implementation of the software is presented. (author)

  17. Recapitulative list of the C.E.A. reports published by the French Atomic Energy Commission (n.757-1062, december 1957-december 1958) supplement to C.E.A. reports n. 593 and 756; Liste recapitulative des rapports C.E.A. publies par le Commissariat a l'Energie Atomique (du n.757 a 1062, decembre 1957-decembre 1958) complement aux rapports C.E.A. n. 593 et 756

    Energy Technology Data Exchange (ETDEWEB)

    Schmiterlow, C G; Cohen, Y [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    Recapitulative list of the C.E.A. reports published by the French Atomic Energy Commission. (number 757-1062, december 1957 - december 1958). Supplement to C.E.A. reports number 593 and 756. (author) [French] Liste recapitulative des rapports C.E.A. publies par le Commissariat a l'Energie Atomique (du numero 757 au numero 1062, decembre 1957 - decembre 1958). Complement aux rapports C.E.A. numero 593 et 756. (auteur)

  18. Significance of the fuel cycle aspects in CEA studies on future nuclear systems

    International Nuclear Information System (INIS)

    Carre, F.; Thomas, J.B.; Boidron, M.

    2001-01-01

    Nuclear energy has unique assets to meet the requirements for a sustainable development in terms of economic competitiveness, environmental friendliness and natural resources saving. Future nuclear system studies conducted by the CEA aim at investigating and developing promising technologies for the medium and the long term for reactors, fuels and the fuel cycle to make nuclear power eligible as one of the major energy sources of the sustainable development. It also aims at maintaining at the best possible level the expertise and the technologies that the CEA will be able to bring to future national and international projects likely to meet market needs in the next decades, which are still uncertain both in terms of performances and time scale. Progress for future nuclear systems is principally sought in the following areas: reinforced economic competitiveness against other available electricity generation means, with a special emphasis put on reducing the investment cost; enhanced safety, especially through an increased resistance to core damages in case of severe accident, and whenever possible by dedicated strategies to exclude core melting; cleanliness through minimising the production of long lived radioactive waste; resource saving through an optimum utilisation of the available resources of fissile and fertile materials; enhanced resistance to proliferation risks; potentialities for other applications than electricity production. (author)

  19. Touch And Go Camera System (TAGCAMS) for the OSIRIS-REx Asteroid Sample Return Mission

    Science.gov (United States)

    Bos, B. J.; Ravine, M. A.; Caplinger, M.; Schaffner, J. A.; Ladewig, J. V.; Olds, R. D.; Norman, C. D.; Huish, D.; Hughes, M.; Anderson, S. K.; Lorenz, D. A.; May, A.; Jackman, C. D.; Nelson, D.; Moreau, M.; Kubitschek, D.; Getzandanner, K.; Gordon, K. E.; Eberhardt, A.; Lauretta, D. S.

    2018-02-01

    NASA's OSIRIS-REx asteroid sample return mission spacecraft includes the Touch And Go Camera System (TAGCAMS) three camera-head instrument. The purpose of TAGCAMS is to provide imagery during the mission to facilitate navigation to the target asteroid, confirm acquisition of the asteroid sample, and document asteroid sample stowage. The cameras were designed and constructed by Malin Space Science Systems (MSSS) based on requirements developed by Lockheed Martin and NASA. All three of the cameras are mounted to the spacecraft nadir deck and provide images in the visible part of the spectrum, 400-700 nm. Two of the TAGCAMS cameras, NavCam 1 and NavCam 2, serve as fully redundant navigation cameras to support optical navigation and natural feature tracking. Their boresights are aligned in the nadir direction with small angular offsets for operational convenience. The third TAGCAMS camera, StowCam, provides imagery to assist with and confirm proper stowage of the asteroid sample. Its boresight is pointed at the OSIRIS-REx sample return capsule located on the spacecraft deck. All three cameras have at their heart a 2592 × 1944 pixel complementary metal oxide semiconductor (CMOS) detector array that provides up to 12-bit pixel depth. All cameras also share the same lens design and a camera field of view of roughly 44° × 32° with a pixel scale of 0.28 mrad/pixel. The StowCam lens is focused to image features on the spacecraft deck, while both NavCam lens focus positions are optimized for imaging at infinity. A brief description of the TAGCAMS instrument and how it is used to support critical OSIRIS-REx operations is provided.

  20. Flux distribution by neutrons semi-conductors detectors during the startup of the EL4 reactor

    International Nuclear Information System (INIS)

    Fuster, S.; Tarabella, A.

    1967-01-01

    The Cea developed neutron semi-conductors detectors which allows a quasi-instantaneous monitoring of neutrons flux distribution, when placed in a reactor during the tests. These detectors have been experimented in the EL4 reactor. The experiment and the results are presented and compared with reference mappings. (A.L.B.)

  1. New high density MTR fuel. The CEA-CERCA-COGEMA development program

    International Nuclear Information System (INIS)

    Languille, A.; Durand, J.P.; Gay, A.

    1999-01-01

    The development of a new generation of LEU, high in density and with reprocessing capacities MTR fuel, is a key issue to provide reactor operators with a smooth operation which is necessary for a long term development of Nuclear Energy. In the RRFM'98 meeting, a joint contribution of CEA, CERCA and COGEMA presented a technical classification of the potential candidates uranium alloys. In this paper this MTR working group presents the development program of a new high density fuel. This program is composed of three main steps: Basic Data analysis and collection, Plate Tests (Irradiation and Post Irradiation Examinations) and Lead Test Assemblies (Irradiation and Post Irradiation Examinations). The goal to be reached is to make this new fuel available before the end of the present US return policy. (author)

  2. Control of effluents and environmental surveillance of the CEA centres. 1997 status; Controle des rejets et surveillance de l'environnement des centres CEA. Bilan 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-01

    The environmental quality in the vicinity of CEA facilities is a major concern of the safety policy of the CEA. The aim of this document is to inform the public about the gaseous and liquids radioactive effluents released by the CEA centres under the permission of the ministry. It provides a status of the effluents and of the radioactivity levels measured near the CEA centres in 1997, using air, water, vegetation and milk samples. A comparison is made with the measurements performed during the 1993-1996 period. The data presented comes from the regulatory registers transmitted to the agency for the protection against ionizing radiations (OPRI) which belongs to the ministry of health. (J.S.)

  3. General safety orientations of the Jules Horowitz Reactor Project (JHRP)

    International Nuclear Information System (INIS)

    Tremodeux, P.; Fiorini, G.L.

    2000-01-01

    After a brief reminder of the JHR purpose, the document outlines the General Safety related Orientations/Recommendations used for the design and the safety assessment of the facility. As far as the JHR design is new, the safety philosophy adopted for this reactor will be as consistent as possible with that recommended for future (power...) reactors. The general recommendations developed in the paper are: the general nuclear safety approach for the design, operation and analysis with, in particular, the adoption of the Defence In Depth principle; the general safety objectives in terms of radiological consequences; the use of Probabilistic Safety Studies; quality assurance. The 'Defence in Depth' concept using amongst others the 'Barrier' principle remains the basis of the JHR safety. 'Defence In Depth' is applied both to design and operation. Its adequacy is checked during the safety assessment and the paper gives the technical recommendations that should allow the designer to implement this concept into the final design. Built mainly for experimental irradiation the JHR facilities will be handled according to conventional or new operation rules which could put materials under stress and entail handling errors. Specific recommendations are defined to take into account the corresponding peculiarities; they are discussed in the paper. The safety design of the JHR takes into account the experience accumulated through the CEA experimental irradiation programmes, which represents several dozen reactor years; the consultation of CEA reactor facilities operators is ongoing. The corresponding feedback is shortly described. Recommendations related to maintenance and associated operation are indicated as well as those regarding the human factor. Details are given on the JHR safety practical implementation through the CEA/DRN Safety approach. Details of the corresponding Safety Objectives are also discussed. Finally the designer position on the role of probabilistic safety

  4. Teaching sodium fast reactor technology and operation for the present and future generations of SFR users

    International Nuclear Information System (INIS)

    Latge, Christian; Rodriguez, Gilles; Baque, Francois; Leclerc, Arnaud; Martin, Laurent; Vray, Bernard; Romanetti, Pascale

    2011-01-01

    This paper provides a description of the education and training activities related to sodium fast reactors, carried out respectively in the French Sodium and Liquid Metal School (ESML) created in 1975 and located in France (at the CEA Cadarache Research Centre), in the Fast Reactor Operation and Safety School (FROSS) created in 2005 at the Phenix plant, and in the Institut National des Sciences et Techniques Nucleaires (INSTN). It presents their recent developments and the current collaborations throughout the world with some other nuclear organizations and industrial companies. Owing to these three entities, CEA provides education and training sessions for students, researchers, and operators involved in the operation or development of sodium fast reactors and related experimental facilities. The sum of courses provided by CEA through its sodium school, FROSS, and INSTN organizations is a unique valuable amount of knowledge on sodium fast reactor design, technology, safety and operation experience, decommissioning aspects and practical exercises. It is provided for the national demand and, since the last ten years, it is extensively opened to foreign countries. Over more than 35 years, the ESML, FROSS, and INSTN have demonstrated their flexibility in adapting their courses to the changing demand in the sodium fast reactor field, operation of PHENIX and SUPERPHENIX plants, and decommissioning and dismantling operations. The results of this ambitious and constant strategy are first sharing of knowledge obtained from experimental studies carried out in research laboratories and operational feedback from reactors, secondly standardized information on safety, and finally the creation of a 'sodium community' that debates, shares the knowledge, and suggests new tracks for a better definition of design and operating rules. (author)

  5. Intensified follow-up in colorectal cancer patients using frequent Carcino-Embryonic Antigen (CEA) measurements and CEA-triggered imaging : Results of the randomized "CEAwatch" trial

    NARCIS (Netherlands)

    Verberne, C. J.; Zhan, Z.; van den Heuvel, E.; Grossmann, I.; Doornbos, P. M.; Havenga, K.; Manusama, E.; Klaase, J.; van der Mijle, H. C. J.; Lamme, B.; Bosscha, K.; Baas, P.; van Ooijen, B.; Nieuwenhuijzen, G.; Marinelli, A.; van der Zaag, E.; Wasowicz, D.; de Bock, G. H.; Wiggers, T.

    Aim: The value of frequent Carcino-Embryonic Antigen (CEA) measurements and CEA-triggered imaging for detecting recurrent disease in colorectal cancer (CRC) patients was investigated in search for an evidence-based follow-up protocol. Methods: This is a randomized-controlled multicenter prospective

  6. Thermohydraulics of reactors

    International Nuclear Information System (INIS)

    Delhaye, J.M.

    2008-01-01

    This scientific and technical handbook about PWR reactors thermohydraulics is the result of many years of teaching in the framework of the CEA-INSTN's atomic engineering training courses, in engineering schools and during continuing training activities. Its main goal is to present in a rigorous and pedagogical way the basic knowledge necessary for the understanding and modeling of single phase and two-phase thermohydraulic phenomena encountered during the design and operation of nuclear reactors. In particular, heat transfers in two-phase flows are presented in a detailed way. Most chapters include some nuclear engineering examples of application of the studied concepts, and some exercises aiming at mastering these concepts. Each example or exercise is accompanied by its detailed solution. Content: - thermohydraulic characteristics of reactors; - design and thermal dimensioning of reactors; - thermal engineering of the fuel element; - two-phase flow configurations in ducts; - recalls about single-phase flow equations; - basic equations for two-phase flows; - modeling of two-phase flows inside ducts; - pressure drops in ducts; - boiling and vapor condensation heat transfers; - two-phase flow instabilities in ducts; - two-phase flow blocking; thermohydraulics of naval propulsion reactors

  7. Astrid (fast breeder nuclear reactor)

    International Nuclear Information System (INIS)

    2014-01-01

    This document presents ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration), a French project of sodium-cooled fast breeder reactor, fourth generation reactor which should be fuelled by uranium 238 rather than uranium 235, and should therefore need less extracted natural uranium to produce electricity. The operation principle of fast breeder reactors is described. They notably directly consume plutonium, allow an easier radioactive waste management as they transform long life radioactive elements into shorter life elements by transmutation. The regeneration process is briefly described, and the various operation modes are evoked (iso-generator, sub-generator, and breeder). Some peculiarities of sodium-cooled reactors are outlined. The Astrid operation principle is described, its main design innovations outlined. Various challenges are discussed regarding safety of supply and waste processing, and the safety of future reactors. Major actors are indicated: CEA, Areva, EDF, SEIV Alcen, Toshiba, Rolls Royce, and Comex. Some key data are indicated: expected lifetime, expected availability rate, cost. The projected site is Marcoule and fast breeder reactors operated or under construction in the world are indicated. The document also proposes an overview of the background and evolution of reactors of 4. generation

  8. Review of Past Reactor Activities in Italy, April 1975

    International Nuclear Information System (INIS)

    Pierantoni, P.

    1975-01-01

    Since the last meeting of the International Working Group on Fast Reactors the natural vocation of the italian program to a cooperation, illustrated on many occasions, has found factual confirmation. As well-known, a broad partnership with France has been entered into. Four agreements have been concluded, towards May-June 1974 - between C.E.A. and C.N.E.N. for the ulterior development of the French filière and the construction and use of PEC; - between C.E.A. and NIRA for the license on the system; - between C.E.A. and AGIP-NUCLEARE for the fabrication of fuel for fast reactors; - between TECHNICATOME and NIRA for the preparation of the offer and the later construction of Super-Phenix. Those agreements are in the full logic of the previous one passed between the producers E.d.F., ENEL and R.W.E. for the construction of the first two commercial-size plants, extrapolated from Phenix and S.N.R. 300. In particular the NERSA society, acting as client for Super-Phenix, has been founded by those same producers and will receive the offer now prepared by a joint team. The new orientation of the programme and the validity of the previous agreements for its implementation have been confirmed at governmental level by the Interministerial Economic Planning Committee (CIPE), which has also approved the third CNEN's five years Plan

  9. Cancer imaging with CEA antibodies: historical and current perspectives.

    Science.gov (United States)

    Goldenberg, D M

    1992-01-01

    This article reviews the history and status of cancer imaging with radiolabeled antibodies against carcinoembryonic antigen (CEA). Although CEA and many other cancer-associated antigens are not distinct for neoplasia, the quantitative increase of these markers in malignant tissues provides a sufficient differential for selective antibody targeting. Animal studies with xenografted human tumors provided the first evidence of the prospects of this technology, followed by initial clinical success with purified goat whole IgG antibodies to CEA, labeled with 131I and with the use of dual-isotope subtraction methods. Subsequently, improved and earlier imaging could be accomplished with monoclonal antibody fragments, which then would permit the use of shorter-lived radionuclides, such as 111In, 123I, and 99mTc. The preferred use of a monoclonal anti-CEA IgG Fab' fragment, labeled with 99mTc by a recently developed, simple and rapid kit, has enabled the detection of small lesions, including those in the liver, within 4 h of injection. By means of SPECT imaging, a high sensitivity and specificity for RAID could be achieved.

  10. Postoperative serum CEA level as predictive factor for survival in patients with colorectal cancer

    International Nuclear Information System (INIS)

    Lemberger, J.J.; Bogar, M.L.; Takacs Kucsera, M.F.; Csernetics, I.F.

    2002-01-01

    Aim: It is known that routine follow-up of patients with resected colorectal cancer includes serial CEA determinations. In this retrospective study we have investigated relationship between CEA level and survival and whether achieved results enable differentiation of tumors with slow and rapid growth. Material and Methods: Mainly between 1995 and 1999 periodic CEA determination by IRMA were performed in 269 patients after curative resection of colorectal carcinoma. Number of CEA determination/patient were 2-16(median 6). Survival ranged 4,5 and>249,7 months. Based on CEA results patients were divided in group with normal (<10ng/ml) and elevated (=10ng/ml) values regardless of postoperative treatment. Survival curves were computed by Kaplan-Meier method and difference was evaluated by logrank test and difference between proportions. Results:Normal end elevated CEA was found in 193 and 76 patients, respectively. The difference of survival curves between patients with normal and elevated CEA are highly significant (p<0,0001). However, only 10 months after tumor resection is the difference between survived proportions significant suggesting already presence of CEA produced micrometastases contributing to progression of neoplastic process. The mean survival time at normal and elevated CEA values are 142,54±17,86(median 128,60±24,04) and 34,15±4,28 (median 25,20±1,97) months, respectively. No significant difference of survival was found regarding tumor localization. Conclusion:The results show that with regard to CEA level it is possible to divide colorectal tumors on marker negative and positive. Marker negative are with slower growth and relatively good prognosis. Marker positive are associated with elevated CEA level and with considerable shorter survival. Postoperative CEA level is valuable parameter in prediction of patient's outcome

  11. Belgium and France join forces in measuring instrument research. SCK-CEN and CEA are jointly developing an innovative type of gamma detector

    International Nuclear Information System (INIS)

    Vermeeren, L.

    2011-01-01

    Real-time monitoring is extremely important to accurately interpret irradiation experiments in research reactors. SCK-CEN has years of expertise in developing sensors to monitor neutron flux, temperature, gamma radiation, etc. It has been collaborating with the CEA since 2006. Both partners share research and research results in the Laboratoire Commun de Instrumentation. Recently, a joint patent application was made for a new type of sensor to measure gamma rays.

  12. The OPERA loop in the OSIRIS reactor core. Pressurized-water irradiation device to study Advanced Reactor Fuels

    International Nuclear Information System (INIS)

    Lucot, M.; Roche, M.

    1986-09-01

    This loop is designed to allow fuel qualification test, i.d. to allow irradiation of representative parts fuel assemblies operating in thermohydraulic and chemical conditions representative of these of present pressurized water reactors or in development. This paper presents the aims of the installation, the general design and the main specifications with a brief detailed description [fr

  13. Third session: new projects; Session 3: Les Projets nouveaux

    Energy Technology Data Exchange (ETDEWEB)

    Iracane, D. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Dupuy, J.P. [AREVA-Technicatome, 13 - Aix en Provence (France); Perotto, G. [AREVA-Framatome-ANP, 13 - Aix en Provence (France); Ithurralde, G. [Electricite de France (EDF), 13 - Aix en Provence (France); Cabrillat, J.C. [CEA Cadarache, Dir. de l' Energie Nucleaire (DEN), 13 - Saint-Paul-lez-Durance (France); Becle, D. [FRAMATOME, AREVA-FANP, 69 - Lyon (France); Pivet, S. [CEA Bruyeres-le-Chatel, 91 (France); Minguet, J.L. [AREVA-Technicatome, 75 - Paris (France)

    2005-07-01

    The RJH (Jules Horowitz reactor) is a 100 MWth research reactor, cooled and moderated by water, that has been designed to operate with high density (8 g U/cm{sup 3}) and low enrichment fuel (19.75%) uranium molybdenum fuel. Its main neutron performances are expected to be: -) maximum fast neutron flux (E > 0.907 MeV) in the sample: 5.10{sup 14} n/cm{sup 2}/s, -) maximum thermal neutron flux (E < 0.625 eV): 4.10{sup 14} n/cm{sup 2}/s, and -) maximal neutron damage: 16 dpa/year. RJH that will be built on the Cea's site of Cadarache, is scheduled to enter into service in 2014, it will take over the activities of the Osiris reactor and its operating life is planned to be over 50 years long. The Cabri research reactor is located on the Cadarache site, it has been operating since 1962 and is now undergoing important upgrading operations whose aim is to make the facility fit to study the behaviour of new nuclear fuels in accidental situations. The RES test reactor is a facility whose aim is to qualify nuclear fuels and core configurations of existing propulsion reactors onboard of aircraft carriers or submarines and to propose innovative concepts for future propulsion reactors. (A.C.)

  14. Limb-Nadir Matching Using Non-Coincident NO2 Observations: Proof of Concept and the OMI-minus-OSIRIS Prototype Product

    Science.gov (United States)

    Adams, Cristen; Normand, Elise N.; Mclinden, Chris A.; Bourassa, Adam E.; Lloyd, Nicholas D.; Degenstein, Douglas A.; Krotkov, Nickolay A.; Rivas, Maria Belmonte; Boersma, K. Folkert; Eskes, Henk

    2016-01-01

    A variant of the limb-nadir matching technique for deriving tropospheric NO2 columns is presented in which the stratospheric component of the NO2 slant column density (SCD) measured by the Ozone Monitoring Instrument (OMI) is removed using non-coincident profiles from the Optical Spectrograph and InfraRed Imaging System (OSIRIS). In order to correct their mismatch in local time and the diurnal variation of stratospheric NO2, OSIRIS profiles, which were measured just after sunrise, were mapped to the local time of OMI observations using a photochemical boxmodel. Following the profile time adjustment, OSIRIS NO2 stratospheric vertical column densities (VCDs) were calculated. For profiles that did not reach down to the tropopause, VCDs were adjusted using the photochemical model. Using air mass factors from the OMI Standard Product (SP), a new tropospheric NO2 VCD product - referred to as OMI-minus-OSIRIS (OmO) - was generated through limb-nadir matching. To accomplish this, the OMI total SCDs were scaled using correction factors derived from the next-generation SCDs that improve upon the spectral fitting used for the current operational products. One year, 2008, of OmO was generated for 60 deg S to 60 deg N and a cursory evaluation was performed. The OmO product was found to capture the main features of tropospheric NO2, including a background value of about 0.3 x 10(exp 15) molecules per sq cm over the tropical Pacific and values comparable to the OMI operational products over anthropogenic source areas. While additional study is required, these results suggest that a limb-nadir matching approach is feasible for the removal of stratospheric NO2 measured by a polar orbiter from a nadir-viewing instrument in a geostationary orbit such as Tropospheric Emissions: Monitoring of Pollution (TEMPO) or Sentinel-4.

  15. Evaluation of the nuclear installations safety of the CEA in 1998

    International Nuclear Information System (INIS)

    Laverie, M.

    1999-09-01

    Michel Laverie, Director of the nuclear safety and quality at the Cea, took stoke of the CEA nuclear installations in 1998. After a recall of the nuclear safety policy and organization, the author presents the risks factors bound to the CEA activities as the dismantling, the wastes and the human factors. A last part is devoted to the list of the accidents occurred during 1998 in the nuclear installations. Tables and statistics illustrate this analysis. (A.L.B.)

  16. The nuclear instrumentation system of the French 1400 MWe reactors

    International Nuclear Information System (INIS)

    Bourgerette, A.; Mauduit, J.P.

    1993-01-01

    The nuclear instrumentation systems in power reactors in France have made considerable advances thanks to technological progress. The appearance of an integrated digital protection system (SPIN) and the extension of digital techniques have considerably improved performance and operating flexibility. Working on the basis of technology developed jointly with the Nuclear Electronics and Instrumentation Department at the French Atomic Energy Commission (CEA), Framatome and Merlin Gerin have designed the new nuclear instrumentation system for 1400 MW reactors. (authors). 4 figs

  17. 15 CFR 950.7 - Center for Environmental Assessment Services (CEAS).

    Science.gov (United States)

    2010-01-01

    ...) The following are examples of CEAS projects and services: (1) CEAS prepares data-based studies and... experiment design, data analysis, and data management support to project managers and produces merged... global oceanographic data base from observations taken during the First GARP Global Experiment (FGGE). (b...

  18. Identification of CEA-interacting proteins in colon cancer cells and their changes in expression after irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Byong Chul [Colorectal Cancer Branch, Research Institute, National Cancer Center, Goyang (Korea, Republic of); Yeo, Seung Gu [Dept. of Radiation Oncology, Soonchunhyang University College of Medicine, Soonchunhyang University Hospital, Cheonan (Korea, Republic of)

    2017-09-15

    The serum carcinoembryonic antigen (CEA) level has been recognized as a prognostic factor in colorectal cancer, and associated with response of rectal cancer to radiotherapy. This study aimed to identify CEA-interacting proteins in colon cancer cells and observe post-irradiation changes in their expression. CEA expression in colon cancer cells was examined by Western blot analysis. Using an anti-CEA antibody or IgG as a negative control, immunoprecipitation was performed in colon cancer cell lysates. CEA and IgG immunoprecipitates were used for liquid chromatography–tandem mass spectrometry (LC-MS/MS) analysis. Proteins identified in the CEA immunoprecipitates but not in the IgG immunoprecipitates were selected as CEA-interacting proteins. After radiation treatment, changes in expression of CEA-interacting proteins were monitored by Western blot analysis. CEA expression was higher in SNU-81 cells compared with LoVo cells. The membrane localization of CEA limited the immunoprecipitation results and thus the number of CEA-interacting proteins identified. Only the Ras-related protein Rab-6B and lysozyme C were identified as CEA-interacting proteins in LoVo and SNU-81 cells, respectively. Lysozyme C was detected only in SNU-81, and CEA expression was differently regulated in two cell lines; it was down-regulated in LoVo but up-regulated in SNU-81 in radiation dosage-dependent manner. CEA-mediated radiation response appears to vary, depending on the characteristics of individual cancer cells. The lysozyme C and Rab subfamily proteins may play a role in the link between CEA and tumor response to radiation, although further studies are needed to clarify functional roles of the identified proteins.

  19. Identification of CEA-interacting proteins in colon cancer cells and their changes in expression after irradiation

    International Nuclear Information System (INIS)

    Yoo, Byong Chul; Yeo, Seung Gu

    2017-01-01

    The serum carcinoembryonic antigen (CEA) level has been recognized as a prognostic factor in colorectal cancer, and associated with response of rectal cancer to radiotherapy. This study aimed to identify CEA-interacting proteins in colon cancer cells and observe post-irradiation changes in their expression. CEA expression in colon cancer cells was examined by Western blot analysis. Using an anti-CEA antibody or IgG as a negative control, immunoprecipitation was performed in colon cancer cell lysates. CEA and IgG immunoprecipitates were used for liquid chromatography–tandem mass spectrometry (LC-MS/MS) analysis. Proteins identified in the CEA immunoprecipitates but not in the IgG immunoprecipitates were selected as CEA-interacting proteins. After radiation treatment, changes in expression of CEA-interacting proteins were monitored by Western blot analysis. CEA expression was higher in SNU-81 cells compared with LoVo cells. The membrane localization of CEA limited the immunoprecipitation results and thus the number of CEA-interacting proteins identified. Only the Ras-related protein Rab-6B and lysozyme C were identified as CEA-interacting proteins in LoVo and SNU-81 cells, respectively. Lysozyme C was detected only in SNU-81, and CEA expression was differently regulated in two cell lines; it was down-regulated in LoVo but up-regulated in SNU-81 in radiation dosage-dependent manner. CEA-mediated radiation response appears to vary, depending on the characteristics of individual cancer cells. The lysozyme C and Rab subfamily proteins may play a role in the link between CEA and tumor response to radiation, although further studies are needed to clarify functional roles of the identified proteins

  20. Integrated science and engineering for the OSIRIS-REx asteroid sample return mission

    Science.gov (United States)

    Lauretta, D.

    2014-07-01

    Introduction: The Origins, Spectral Interpretation, Resource Identification, and Security-Regolith Explorer (OSIRIS-REx) asteroid sample return mission will survey near-Earth asteroid (101955) Bennu to understand its physical, mineralogical, and chemical properties, assess its resource potential, refine the impact hazard, and return a sample of this body to the Earth [1]. This mission is scheduled for launch in 2016 and will rendezvous with the asteroid in 2018. Sample return to the Earth follows in 2023. The OSIRIS-REx mission has the challenge of visiting asteroid Bennu, characterizing it at global and local scales, then selecting the best site on the asteroid surface to acquire a sample for return to the Earth. Minimizing the risk of exploring an unknown world requires a tight integration of science and engineering to inform flight system and mission design. Defining the Asteroid Environment: We have performed an extensive astronomical campaign in support of OSIRIS-REx. Lightcurve and phase function observations were obtained with UA Observatories telescopes located in southeastern Arizona during the 2005--2006 and 2011--2012 apparitions [2]. We observed Bennu using the 12.6-cm radar at the Arecibo Observatory in 1999, 2005, and 2011 and the 3.5-cm radar at the Goldstone tracking station in 1999 and 2005 [3]. We conducted near-infrared measurements using the NASA Infrared Telescope Facility at the Mauna Kea Observatory in Hawaii in September 2005 [4]. Additional spectral observations were obtained in July 2011 and May 2012 with the Magellan 6.5-m telescope [5]. We used the Spitzer space telescope to observe Bennu in May 2007 [6]. The extensive knowledge gained as a result of our telescopic characterization of Bennu was critical in the selection of this object as the OSIRIS-REx mission target. In addition, we use these data, combined with models of the asteroid, to constrain over 100 different asteroid parameters covering orbital, bulk, rotational, radar

  1. Nondestructive testing at the CEA

    International Nuclear Information System (INIS)

    Colomer, J.; Lucas, G.

    1976-01-01

    The different nondestructive testing methods used at the CEA are presented: X-ray or gamma radiography, X-ray stress analysis, neutron radiography, ultrasonic testing, eddy currents, electrical testing, microwaves, thermal testing, acoustic emission, optical holography, tracer techniques. (102 references are cited) [fr

  2. A synthesis on the HTR scenario studies at CEA - HTR2008-58059

    International Nuclear Information System (INIS)

    Boucher, L.; Greneche, D.

    2008-01-01

    The aim of the studies is to assess the impact of the deployment of an HTR park replacing one part of the current PWR reactors. The other part of the current park is replaced by EPRs. In these scenarios, the annual electricity production is constant at 400 TWhe. This value corresponds roughly to the present nuclear electricity production in France. From 2002 to 2007, an important program study on HTR has been carried out by CEA and AREVA NC under the joint CEA - AREVA NC project 'prospective studies on the management of Plutonium and the back end of the cycle'. This program addresses core physic and scenario studies, and also the back end of the fuel cycle : reprocessing of spent fuel and HTR waste management. Some core physic studies have already been presented in the reference [1]. This paper presents the results of the scenario studies using two concepts: either the standard core of the Gas Turbine Modular Helium Reactor concept (GTMHR) with Uranium or Plutonium fuel, or the Multiple Fuel Rows Core (MFRC) dedicated to the actinide burning. The insertion of a new concept (fuel, reactor, process) must be evaluated in the global electronuclear system with an analysis of the impact on the fuel cycle (Enrichment, Fuel Fabrication, Reactor, Processing, Interim Storage, Waste storage). The scenario studies are used to evaluate different solutions to manage nuclear materials (uranium, plutonium) and wastes (minor actinides and fission products), from the present situation in France (closed cycle with storage of used MOX fuels) until the final equilibrium: mixed nuclear park with EPR and HTR. These studies allow to calculate material flows and inventories of these elements in each step of the fuel cycle. The simulation of transient scenarios from the present situation to the future situation is performed with the COSI code. HTR reactors feature a high flexibility with regard to fuel cycle options. Several versions of core have been investigated, with different type of

  3. Decree no. 96-978 from October 31, 1996 giving permission to the French atomic energy Commission (CEA) to create a basic nuclear installation intended to maintain under supervision and in an intermediate dismantling state the old basic nuclear installation no. 28, named Monts d'Arree-EL 4 nuclear power plant (a decommissioned reactor), in the Monts d'Arree site of the Loqueffret town (Finistere, Brittany)

    International Nuclear Information System (INIS)

    Borotra, F.; Lepage, C.

    1996-01-01

    This decree from the French ministry of industry and postal services gives permission to the CEA to create a new basic nuclear installation, named EL 4D, which is devoted to the storage of materials from the partially dismantled Monts d'Arree EL 4 reactor. Thus, the CEA is allowed to carry out confining works on the reactor building with the closure of all apertures with the exception of the personnel entry sieve, on the circuits and equipments of the reactor vessel with the plugging of fuel channels, heavy water, helium and demineralized water pipes and of the heads of control rod drive mechanisms and other channels, and on the primary coolant circuit outside the reactor vessel and the steam generators with the installation of welded hatches. The irradiated fuels building, the solid wastes repository, the ventilation building, the heavy water and helium circuits, the fuel handling systems and the effluents treatment plant will be completely dismantled. The other buildings will be pulled down. The rest of the decree enumerates the general technical and safety prescriptions which have to be followed in order to ensure the protection of the personnel against ionizing radiations and of the environment against radioactive pollution. (J.S.)

  4. Reactor modification, preparation and operation

    International Nuclear Information System (INIS)

    Weill, J.; Furet, J.; Baillet, J.; Donvez, G.; Duchene, J.; Gras, R.; Mercier, R.; Chenouard, J.; Leconte, J.

    1962-01-01

    In the course of preparations for the dosimetry experiment at the R-B reactor the control and safety equipment of the reactor was found to be inadequate for operation at a constant power level of several watts. After completing the study of control and safety issues by CEA, safety and control were defined for the purpose of the Joint Dosimetry Experiment. Preparations for the Dosimetry Experiment included: installation of equipment for control and safety of the reactor; supplying 6570 Kg of heavy water by UK, reinforcement of the reactor wall on the outside of the building; constructing the protection of the control room; start-up, measuring of the critical heavy water level, and check of control and safety rods worth. After the final check of safety rod mechanisms, eight runs were performed at a power of 5 Watt, and then a 1 k Watt run was carried out and the power stabilized at this power for 30 min by automatic control system

  5. Reactor modification, preparation and operation

    Energy Technology Data Exchange (ETDEWEB)

    Weill, J; Furet, J; Baillet, J; Donvez, G; Duchene, J; Gras, R; Mercier, R [Electronics Dept., Independent Section of Reactor Electronics, Saclay (France); Chenouard, J; Leconte, J [Dept. of Physical Chemistry, Stable Isotopes Section, Saclay (France)

    1962-03-01

    In the course of preparations for the dosimetry experiment at the R-B reactor the control and safety equipment of the reactor was found to be inadequate for operation at a constant power level of several watts. After completing the study of control and safety issues by CEA, safety and control were defined for the purpose of the Joint Dosimetry Experiment. Preparations for the Dosimetry Experiment included: installation of equipment for control and safety of the reactor; supplying 6570 Kg of heavy water by UK, reinforcement of the reactor wall on the outside of the building; constructing the protection of the control room; start-up, measuring of the critical heavy water level, and check of control and safety rods worth. After the final check of safety rod mechanisms, eight runs were performed at a power of 5 Watt, and then a 1 k Watt run was carried out and the power stabilized at this power for 30 min by automatic control system.

  6. Reactor modification, preparation and operation

    Energy Technology Data Exchange (ETDEWEB)

    Weill, J; Furet, J; Baillet, J; Donvez, G; Duchene, J; Gras, R; Mercier, R [Electronics Dept., Independent Section of Reactor Electronics, Saclay (France); Chenouard, J; Leconte, J [Dept. of Physical Chemistry, Stable Isotopes Section, Saclay (France)

    1962-03-15

    In the course of preparations for the dosimetry experiment at the R-B reactor the control and safety equipment of the reactor was found to be inadequate for operation at a constant power level of several watts. After completing the study of control and safety issues by CEA, safety and control were defined for the purpose of the Joint Dosimetry Experiment. Preparations for the Dosimetry Experiment included: installation of equipment for control and safety of the reactor; supplying 6570 Kg of heavy water by UK, reinforcement of the reactor wall on the outside of the building; constructing the protection of the control room; start-up, measuring of the critical heavy water level, and check of control and safety rods worth. After the final check of safety rod mechanisms, eight runs were performed at a power of 5 Watt, and then a 1 k Watt run was carried out and the power stabilized at this power for 30 min by automatic control system.

  7. Serum CEA (carcino-embryonic antigen) monitoring after surgery for cancer of the rectum and colon

    International Nuclear Information System (INIS)

    Reginster, J.Y.; Desaive, C.; Collette, J.; Zangerle, P.F.; Denis, D.; Franchimont, P.

    1984-01-01

    Fifty four patients, operated for colorectal cancer have been followed up for 2 to 100 months after surgery by carcino-embryonic antigen (CEA) determinations and classical, clinical, biological, radiological, echographical, isotopical and tomoscanninvestigations. Each new serum sample has been assayed for CEA with previously collected samples within the same patients. This repetition of CEA on the same samples allows to check the good reproducibility of CEA radioimmunoassay (variation coefficient between assay is less than 10%) and to get a complete profile of CEA level evaluation within the same assay. There is a good correlation between clinical evolution and CEA levels. In 42 patients, CEA levels remained or became normal ( 20 ng ml) at the same time or before clinical and/or paraclinical evidences for metastases or local recurrence. These results showed CEA assay in a quantitative parameter to assess the follow-up of colorectal cancer complementary to clinical, biological, radiological, echographical and isotopical criterias [fr

  8. An Exegetical Note on Plutarch, Isis and Osiris 351E

    Directory of Open Access Journals (Sweden)

    Geert Roskam

    2015-06-01

    Full Text Available In this article, I deal with a short but complex sentence at the end of the first chapter of Plutarch’s Isis and Osiris. Plutarch there says that «the happiness of even the eternal life, which God has obtained as his portion, consists in the fact that the things that come to be do not, through knowledge, fail in advance» (351E. This obscure phrase implies, so I argue, that Plutarch’s providential God has a knowledge of particular contingencies and that this knowledge indeed contributes to his eternal blessedness without affecting His essence.

  9. Fuel assemblies for PWR type reactors: fuel rods, fuel plates. CEA work presentation

    International Nuclear Information System (INIS)

    Delafosse, Jacques.

    1976-01-01

    French work on PWR type reactors is reported: basic knowledge on Zr and its alloys and on uranium oxide; experience gained on other programs (fast neutron and heavy water reactors); zircaloy-2 or zircaloy-4 clad UO 2 fuel rods; fuel plates consisting of zircaloy-2 clad UO 2 squares of thickness varying between 2 and 4mm [fr

  10. Evaluation of Applicability for the Core Protection Method with 4-Channel CEA Positions to OPR-1000 Plants

    International Nuclear Information System (INIS)

    Koo, B. S.; Cho, J. Y.; Song, J. S.

    2008-05-01

    To increase the applicability of research results established during the process of integral reactor development program, a new core protection method with 4-channel CEA positions was applied to the domestic commercial plants and its feasibility was evaluated. To achieve above object, state-of-the-art related to core protection system was analyzed as followings: - Unusual CPC operating experience in Korea - Evaluate the proposals of CPC improvement suggested by CPC Task Force Team - Review the conventional CPC used in Yonggwang and Ulchin plants - Review the Common-Q CPC to be implemented in Shin-Kori Units 1 and 2 - Evaluate the SENTINEL core protection system in US and COPS core protection system in Germany - Examine the applied patents in Korea, US and Japan - Analyze the copyright for computer programs used in core protection system design and license agreement for PWR technology between Westinghouse and Korea. In addition, study for the formation of system, design requirement, algorithm improvement and enhancement of operator interface was performed to apply the newly suggested core protection method to the commercial plants. By adopting this method, it is expected that unnecessary channel of reactor trips will be decreased considerably. Although change of system including CEA must be set forth as a prerequisite to apply this method to the domestic commercial plants as well as scheduled plants, this study suggests the strategy and direction for the development of core protection system in domestic. This study, moreover, will provide the valuable information as a basic data in establishing the detailed development plan for the advanced core protection system in the future

  11. CEA budget in 1982

    Energy Technology Data Exchange (ETDEWEB)

    1981-12-01

    In 1982, the amount of the CEA budget will be 13.4 billions French Francs. The main characteristics are the priority for employment and investments. In this budget programs are adapted to fit R and D to the government policy: innovation, industrial valorization and fundamental research especially thermonuclear fusion and in the electronuclear field to safety, reprocessing and radioactive waste management.

  12. Physics experiment on the Dragon reactor

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, C.

    1974-10-15

    The paper describes a set of DRAGON experiments planned to measure burn-up effects in DRAGON irradiated fuel. Irradiated fuel elements from DRAGON are to be subjected to reactivity measurements in the HECTOR experimental reactor to infer the residual U235 content followed by isotopic analyses at CEA laboratories in 1975. Fast neutron damage to DRAGON graphite is compared to fast neutron dose measurements using Ni58 (n,p) Co58 activation wires in both DRAGON and the DIDO MTR. Gamma scanning of irradiated fuel elements are used to compare axial power profiles to those derived from two-dimensional and three-dimensional calculations of the DRAGON reactor.

  13. Demonstration of monoclonal anti-carcinoembryonic antigen (CEA) antibody internalization by electron microscopy, western blotting and radioimmunoassay.

    Science.gov (United States)

    Tsaltas, G; Ford, C H; Gallant, M

    1992-01-01

    One of the important factors affecting the action of monoclonal antibodies (Mabs) or immunoconjugates on tumour sites depends on whether the Mab is internalized by the cancer cells in question. The underexplored subject of internalization is discussed in this paper, and a number of in vitro techniques for investigating internalization are evaluated, using a model which consists of a well characterized anti-carcinoembryonic antigen (anti-CEA) Mab and a number of CEA expressing human cancer cell lines. Employing two alternative radiolabeling assays, evidence for internalization of the anti-CEA Mab by a CEA-positive colorectal cancer cell line (LS174T) was obtained throughout the time intervals examined (5 min to 150 min). Electronmicroscopy employing horseradish-peroxidase labeled anti-CEA Mab and control antibody permitted direct visualization of anti-CEA Mab-related staining in intracellular compartments of a high CEA-expressor human colorectal cell line (SKCO1). Finally Western blots of samples derived from cytosolic and membrane components of solubilized cells from lung and colonic cancer cell lines provided evidence for internalized anti-CEA Mab throughout seven half hour intervals, starting at 5 minutes. Internalized anti-CEA was detected in all CEA expressing cell lines (LS174T, SKCO1, BENN) but not in the case of a very low CEA expressor line (COLO 320).

  14. Regarding the old Cea factory of the Bouchet

    International Nuclear Information System (INIS)

    Anon

    1997-10-01

    This article si devoted to the Cea site of the Bouchet. Radiation monitoring have been made and the information about it, given to the populations around the site. The wastes with a value upper than this one chosen for low activity wastes have been sent to the storage center of Manche plant, the other ones whom activity level was lower than this one advocated for low level radioactive wastes were used for the base of A87 motorway. The two little rivers have been cleaned out and the sediments tipped out in the decantation basin of the Cea site. Radiation monitoring for the radon have to be made to control the right progress of these decontamination operations. All these operations have been made in dialogue with S.N.P.E.( the national society of powders and explosives), the D.R.I.R.E.( regional direction of research industry and environment), O.P.R.I. (office of protection against ionizing radiations) and the Cea. (N.C.)

  15. OSIRIS-REx Asteroid Sample Return Mission Image Analysis

    Science.gov (United States)

    Chevres Fernandez, Lee Roger; Bos, Brent

    2018-01-01

    NASA’s Origins Spectral Interpretation Resource Identification Security-Regolith Explorer (OSIRIS-REx) mission constitutes the “first-of-its-kind” project to thoroughly characterize a near-Earth asteroid. The selected asteroid is (101955) 1999 RQ36 (a.k.a. Bennu). The mission launched in September 2016, and the spacecraft will reach its asteroid target in 2018 and return a sample to Earth in 2023. The spacecraft that will travel to, and collect a sample from, Bennu has five integrated instruments from national and international partners. NASA's OSIRIS-REx asteroid sample return mission spacecraft includes the Touch-And-Go Camera System (TAGCAMS) three camera-head instrument. The purpose of TAGCAMS is to provide imagery during the mission to facilitate navigation to the target asteroid, confirm acquisition of the asteroid sample and document asteroid sample stowage. Two of the TAGCAMS cameras, NavCam 1 and NavCam 2, serve as fully redundant navigation cameras to support optical navigation and natural feature tracking. The third TAGCAMS camera, StowCam, provides imagery to assist with and confirm proper stowage of the asteroid sample. Analysis of spacecraft imagery acquired by the TAGCAMS during cruise to the target asteroid Bennu was performed using custom codes developed in MATLAB. Assessment of the TAGCAMS in-flight performance using flight imagery was done to characterize camera performance. One specific area of investigation that was targeted was bad pixel mapping. A recent phase of the mission, known as the Earth Gravity Assist (EGA) maneuver, provided images that were used for the detection and confirmation of “questionable” pixels, possibly under responsive, using image segmentation analysis. Ongoing work on point spread function morphology and camera linearity and responsivity will also be used for calibration purposes and further analysis in preparation for proximity operations around Bennu. Said analyses will provide a broader understanding

  16. Rosácea fulminante: relato de caso

    Directory of Open Access Journals (Sweden)

    José Otávio Alquezar Gozzano

    2016-10-01

    Full Text Available Introdução: Rosácea fulminante (RF ou pioderma facial é uma doença rara, descrita em 1940 por Kierland e O’Leary. É considerada uma variante extrema de rosácea conglobata, esta, consiste em formação de placas e abscessos hemorrágicos na pele. A RF tem sua etiologia desconhecida, porém há teorias que relacionam seu acometimento com a variação de hormônios femininos e a ingestão de vitamina B12. A RF é frequente em mulheres, principalmente pós- adolescentes. Apresenta-se abruptamente na face, amiúde na região mento- mandibular, através de pápulas inflamatórias, pústulas, cistos e nódulos com comedões escassos ou inexistentes, além de abcessos, sem manifestações sistêmicas e com a recidiva rara. Seu diagnóstico é fundamentalmente clínico, apenas com a história do paciente, sem necessidade de exames complementares. Para o tratamento, são utilizados corticoides orais, isotretinoína oral e antibióticos a fim de minimizar as sequelas físicas e psicológicas. Objetivo: Relatar caso de paciente com diagnóstico de rosácea fulminante. Metodologia: Paciente diagnosticada com rosácea fulminante atendida em serviço ambulatorial e revisão de literatura. Relato de caso: Paciente do sexo feminino, 19 anos, refere lesões súbitas em face há uma semana. Nega quadro acneico anterior, histórias de alergias e outras comorbidades. Relata ausência de uso de anticoncepcionais orais há 5 meses e data de última menstruação há 3 semanas, sem atraso menstrual. Ao exame: pápulas eritematosas e pústulas, além de pequenos nódulos inflamatórios na face. Hipótese diagnóstica: RF. Como conduta, foi prescrito tetraciclina. Conclusões: A RF é uma forma infrequente de rosácea, sendo importante o diagnóstico precoce e tratamento eficaz, a fim de melhorar a qualidade de vida do paciente.

  17. Control of effluents and environmental surveillance of the CEA centres. 1997 status

    International Nuclear Information System (INIS)

    1998-06-01

    The environmental quality in the vicinity of CEA facilities is a major concern of the safety policy of the CEA. The aim of this document is to inform the public about the gaseous and liquids radioactive effluents released by the CEA centres under the permission of the ministry. It provides a status of the effluents and of the radioactivity levels measured near the CEA centres in 1997, using air, water, vegetation and milk samples. A comparison is made with the measurements performed during the 1993-1996 period. The data presented comes from the regulatory registers transmitted to the agency for the protection against ionizing radiations (OPRI) which belongs to the ministry of health. (J.S.)

  18. Network and system diagrams revisited: Satisfying CEA requirements for causality analysis

    International Nuclear Information System (INIS)

    Perdicoulis, Anastassios; Piper, Jake

    2008-01-01

    Published guidelines for Cumulative Effects Assessment (CEA) have called for the identification of cause-and-effect relationships, or causality, challenging researchers to identify methods that can possibly meet CEA's specific requirements. Together with an outline of these requirements from CEA key literature, the various definitions of cumulative effects point to the direction of a method for causality analysis that is visually-oriented and qualitative. This article consequently revisits network and system diagrams, resolves their reported shortcomings, and extends their capabilities with causal loop diagramming methodology. The application of the resulting composite causality analysis method to three Environmental Impact Assessment (EIA) case studies appears to satisfy the specific requirements of CEA regarding causality. Three 'moments' are envisaged for the use of the proposed method: during the scoping stage, during the assessment process, and during the stakeholder participation process

  19. The experimental program of neutronphysics for advanced water reactors

    International Nuclear Information System (INIS)

    Martin-Deider, L.; Cathalu, S.; Santamarina, A.; Gomit, M.

    1985-11-01

    The C.E.A. and E.D.F. has jointly undertaken a program of experimental studies on under-moderated water lattices, with mixed oxide fuel UO 2 -PuO 2 . Undermoderated lattices offer high conversion ratios. This type of lattice could limit in the future the natural uranium consumption of pressurized water reactors. This experimental program is aimed at qualifying neutron transport calculations in a large range of moderating ratio (between 0.5 and 1.5). It includes three experiments: ERASME, a critical experiment of large size in the EOLE reactor at Cadarache; ICARE, an irradiation experiment in the MELUSINE reactor at Grenoble; and an experiment to measure the reactivity effects by oscillations in the MINERVE reactor at Cadarache [fr

  20. From fundamental mode to the PWR type reactors blow off: physical analysis and contribution to the qualification of calculation tools

    International Nuclear Information System (INIS)

    Maghnouj, A.

    1996-01-01

    The work reported in this thesis centres on the resolution of reactor physics problems posed by the use in pressurised water reactors of fuel assemblies containing mixed uranium-plutonium oxide fuel (MOX). The work is essentially dependent on the results of the EPICURE experimental programme carried out between 1988 and 1994 in the reactor EOLE at the Cadarache Research Centre of the CEA. Our contribution to the validation of the computer program APOLLO2 and of its nuclear data library CEA93 shows that this code system satisfactorily calculates the neutronic characteristics of PWR cores. The validation of the experiments has provided useful information concerning the modifications required to be made to the library CEA93, which is based on the basic library of evaluated nuclear data, JEF2. This approach should now be extended to a wider basis of reactor experimental data. The studies of methods for calculating coolant voiding coefficients has made it possible to select suitable methods based on the available deterministic methods of transport theory in 2 ad 3 dimensions. These schemes have given results in satisfactory agreement with the measurements made in EPICURE programme for both local and total coolant voiding. It would now be worth while to validate the chosen methods by comparisons with calculations made using continuous energy Monte Carlo methods. (author)

  1. Compton scattering collision module for OSIRIS

    Science.gov (United States)

    Del Gaudio, Fabrizio; Grismayer, Thomas; Fonseca, Ricardo; Silva, Luís

    2017-10-01

    Compton scattering plays a fundamental role in a variety of different astrophysical environments, such as at the gaps of pulsars and the stagnation surface of black holes. In these scenarios, Compton scattering is coupled with self-consistent mechanisms such as pair cascades. We present the implementation of a novel module, embedded in the self-consistent framework of the PIC code OSIRIS 4.0, capable of simulating Compton scattering from first principles and that is fully integrated with the self-consistent plasma dynamics. The algorithm accounts for the stochastic nature of Compton scattering reproducing without approximations the exchange of energy between photons and unbound charged species. We present benchmarks of the code against the analytical results of Blumenthal et al. and the numerical solution of the linear Kompaneets equation and good agreement is found between the simulations and the theoretical models. This work is supported by the European Research Council Grant (ERC- 2015-AdG 695088) and the Fundao para a Céncia e Tecnologia (Bolsa de Investigao PD/BD/114323/2016).

  2. OSIRIS-REx Touch-and-Go (TAG) Mission Design for Asteroid Sample Collection

    Science.gov (United States)

    May, Alexander; Sutter, Brian; Linn, Timothy; Bierhaus, Beau; Berry, Kevin; Mink, Ron

    2014-01-01

    The Origins Spectral Interpretation Resource Identification Security Regolith Explorer (OSIRIS-REx) mission is a NASA New Frontiers mission launching in September 2016 to rendezvous with the near-Earth asteroid Bennu in October 2018. After several months of proximity operations to characterize the asteroid, OSIRIS-REx flies a Touch-And-Go (TAG) trajectory to the asteroid's surface to collect at least 60 g of pristine regolith sample for Earth return. This paper provides mission and flight system overviews, with more details on the TAG mission design and key events that occur to safely and successfully collect the sample. An overview of the navigation performed relative to a chosen sample site, along with the maneuvers to reach the desired site is described. Safety monitoring during descent is performed with onboard sensors providing an option to abort, troubleshoot, and try again if necessary. Sample collection occurs using a collection device at the end of an articulating robotic arm during a brief five second contact period, while a constant force spring mechanism in the arm assists to rebound the spacecraft away from the surface. Finally, the sample is measured quantitatively utilizing the law of conservation of angular momentum, along with qualitative data from imagery of the sampling device. Upon sample mass verification, the arm places the sample into the Stardust-heritage Sample Return Capsule (SRC) for return to Earth in September 2023.

  3. Aeroacoustics research in Europe : the CEAS-ASC report on 1997 highlights

    NARCIS (Netherlands)

    Rienstra, S.W.

    1998-01-01

    This paper is a report on the highlights of aeroacoustics research and development in Europe in 1997, compiled from information provided in the CEAS Aeroacoustics Specialists Committee (ASC). The Confederation of European Aerospace Societies (CEAS) comprises the national Aerospace Societies of

  4. Carcinoembryonic antigen (CEA)

    International Nuclear Information System (INIS)

    Ephraim, K.H.; Cox, P.H.; Hamer, C.J.A. v.d.; Berends, W.; Delhez, H.

    1977-01-01

    The carcinoembryonic antigen (CEA) is a complex of antigen determinants and also the carrier of these determinants. Chemically it is a glycoprotein. Its occurrence in blood serum or urine is correlated with malignant disease. Several radioimmunoassays (RIA) have been developed, one by Hoffmann-Laroche and one by the Rotterdam Radiotherapeutic Institute. Both methods and the Hoffmann assay kit are tested. Specifications are given for isolation of the antigen, preparation of the antiserum, and the execution of the RIA. Biochemical and clinical aspects are discussed

  5. Study relating to the physico-chemical behaviour of heavy water in nuclear reactors; Etudes relatives au comportement physico-chimique de l'eau lourde dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J; Dirian, G; Roth, E; Vignet, P; Platzer, R [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1959-07-01

    Chemical and isotope pollution, and radiolytic decomposition are the two most important ways in which heavy water becomes degraded in nuclear reactors. Chemical pollution has led to the creation of ion exchange purification loops specially designed for reactors: the report contains a description in detail of the application of this purification method in CEA research reactors, including the analysis required, results obtained, and their interpretation. The intelligence obtained on radiolytic decomposition with the same facilities is also discussed, as well as the recombination apparatus and control equipment utilized. Finally, investigation to date in the CEA on recombination circuits for power reactors is also discussed. (author) [French] Parmi les degradations subies par l'eau lourde dans les reacteurs nucleaires, les deux plus importantes sont la pollution chimique et isotopique et la decomposition radiolytique. La pollution chimique a conduit a mettre au point pour le cas particulier des reacteurs, des circuits d'epuration par echange d'ions. On decrit ici en detail la mise en oeuvre de cette methode dans les reacteurs de recherche du CEA; les controles qu'elle necessite, les resultats obtenus et leur interpretation. En ce qui concerne la dissociation radiolytique de l'eau, les renseignements obtenus sur ces memes reacteurs sont communiques, ainsi que les details des dispositifs de recombinaison et des moyens de controle. Enfin, on fait le point des etudes poursuivies au CEA sur ces memes problemes de recombinaison dans le cas des reacteurs de puissance. (auteur)

  6. CA 19-9 as a marker in addition to CEA to monitor colorectal cancer.

    Science.gov (United States)

    Stiksma, Jolanda; Grootendorst, Diana C; van der Linden, Peter Willem G

    2014-12-01

    Carcinoembryonic antigen is the commonly used tumor marker in patients with colorectal cancer, and CA 19-9 might be an additional marker. The aim of this retrospective study was to investigate whether CA 19-9 levels can be used to monitor the disease process in patients with colorectal cancer who had no elevated CEA levels. The secondary aim was to determine if preoperative increased levels of CEA and CA 19-9 were associated with mortality. Two sets of data from patients with histologically confirmed colorectal cancer, were included in a single-center study. First, patients with a minimum of 3 serial measurements of CA 19-9 and CEA tumor markers were related to the clinical course of their disease. Second, patients with preoperative levels of CEA and CA 19-9 were related to survival. In patients with colorectal cancer and 3 serial measurements of tumor markers, 7.3% had only increased CA 19-9 levels without increased CEA levels, and 55.4% of the patients had an increase of CA 19-9 and CEA levels. In the patients with available preoperative markers, patients with only an increase of CA 19-9 had a significantly decreased 5-year survival compared with patients with an increase of only CEA (P = .013). CA 19-9 can be used as additional marker to follow the disease process in patients with colorectal cancer without an increase in CEA level. Patients with preoperative increased CA 19-9 level had a poorer 5-year survival than patients with preoperative increased CEA levels. Copyright © 2014 Elsevier Inc. All rights reserved.

  7. Major upgrade of the reactor dosimetry interpretation methodology used at CEA. Architecture description

    International Nuclear Information System (INIS)

    Gregoire, Gilles; Destouches, Christophe; Beretz, Daniel; Bourganel, Stephane

    2009-01-01

    One of the main objectives of reactor dosimetry is the determination of the physical parameters characterizing the neutron field in which studied samples are irradiated. These values, from neutron spectrum to reaction rates are used on the one hand in experimental reactors to carry out the follow-up of the irradiation and to qualify the neutron calculation (modeling scheme for the experiment) and, on the other hand in power reactors for the follow-up of the damaging of vessel and internals. Neutron parameters are obtained from the treatment of dosimeter's activities which have suitable reactions (response functions and radioactive emissions). Then, activities are analyzed using nuclear data, neutron computation results and data characterizing the conditions of irradiation (temporal and technological data, changes of location...). This current interpretation process presents limitations coming mainly from the calculations tools and the nuclear data knowledge. But nowadays due to, first the improvement of the neutron calculation tools, a full 3D Monte Carlo reactor modeling providing reaction in a point wise format is now possible in a reasonable time, and second, recent releases of the international nuclear data libraries, JEFF3.1, ENDFB7 for transport calculation and IRDF2002 and EAF2007 for dosimetry libraries, a deep renewal of the reactor dosimetry interpretation process has been engaged. In addition, uncertainties associated to the results are derived in a rigorous way using simulation methods. This paper lists the main improvements of the neutron calculation codes and of the international nuclear data libraries. The principle of new interpretation process is then detailed. The general software architecture is then described, especially open-source tools chosen for the implementation. The paper finally analyzes expected improvements. (author)

  8. Light-water reactors. Safety problems and related studies in France

    International Nuclear Information System (INIS)

    Lelievre, J.

    1975-01-01

    The program of theoretical and experimental studies developed by the CEA on the safety of PWR reactors is presented: studies relative to the consequences of a LOCA following a rupture of the primary system, studies relative to fuel element behavior, studies on steels, reliability studies and studies of non-destructive testing methods [fr

  9. Safety approach and R and D program for future french sodium-cooled fast reactors

    International Nuclear Information System (INIS)

    Beils, Stephane; Carluec, Bernard; Devictor, Nicolas; Fiorini, Gian Luigi; Sauvage, Jean Francois

    2011-01-01

    This paper presents briefly the safety approach as well as the R and D program that is underway to support the deployment of future French Sodium-Cooled fast Reactors (SFRs): A) Safety objectives and principles for future reactors. The content of the first section reflects the works of AREVA, CEA, and EDF concerning the safety orientations for the future reactors. The availability of such orientations and requirements for the SFRs has to allow introducing and managing the process that will lead to the detailed definition of the safety approach, to the selection of the corresponding safety options, and to the identification and motivation of the supporting R and D. B) Strategy and roadmap in support of the R and D for future SFRs. This section describes the R and D program led jointly by CEA, EDF, and AREVA, which has been developed with the objectives to be able to preliminarily define, by 2012, the safety orientations for the future SFRs, and to deduce from them the characteristics of the ASTRID prototype. (author)

  10. Jules Horowitz reactor (RJH): its design

    International Nuclear Information System (INIS)

    Dupuy, J.P.

    2002-01-01

    This article presents the design of the new irradiation facility (Jules Horowitz reactor) that is planned to be built on the Cadarache site of Cea. 2 principles have been followed. The first one is based on a physical separation between the systems and activities related to the reactor and the experiments from one hand and the other systems and means dedicated to the treatment of the experimental devices before and after irradiation on the other hand. This first principle implies to build 2 buildings: the reactor building and the nuclear auxiliaries building. Inside the reactor building activities from the reactor itself are separated from those dedicated to experimentation. In order to maximize the efficiency of such a reactor, an important number of simultaneous experiments is expected, which will generate an endless flux of incoming and out-going experiments and as a consequence an important handling work between the different work posts. The second principle aims at easing any handling work without breaking the rules of confinement. The different storing pools, the water pits that lead to the 5 hot cells and the reactor tank will communicate through a water-filled canal that will link the 2 buildings. (A.C.)

  11. Status of the CNES-CEA joint program on space nuclear Brayton systems

    International Nuclear Information System (INIS)

    Carre, F.; Proust, E.; Chaudourne, S.; Keirle, P.; Tilliette, Z.; Vrillon, B.

    1989-01-01

    A Cooperative program between the French Centre National d'Etudes Spatiales (CNES) and the Commissariat a l'Engergie Atomique (CEA) was initiated in 1983, to investigate the possible development of 20 to 200 kWe space nuclear power systems to be launched by the next version of the European launcher, Ariane V. After completion in 1986 of preliminary conceptual studies of a reference 200 kWe turboelectric power system, an additional 3 year study phase was decided, with the double objective of assessing the potential advantage of nuclear power systems versus solar photovoltaic or dynamic systems in the 20 kWe power range, and comparing various reactor candidate technologies and systems options for 20 kWe space nuclear power systems, likely to meet the projected energy needs of future European space missions. The results of this study are discussed by the authors

  12. CEA 2011, a look back at a year of research

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    For this year 2011, marked by the Fukushima accident, the goal is improved safety. This is a key issue being addressed by CEA, while at the same time boosting its R and D on low-carbon energies, defense and security, Health technologies, information technologies and very large research Infrastructures. With more than 650 priority patents filed in 2011, CEA maintains its position as the leading French research organization. CEA stands in 4. place among the European research organizations, in terms of the number of projects (535, including 70 that it coordinates) and financing obtained (nearly euros 55 M) under the European Commission's FP7 framework programme. CEA's civil programs are 30% funded from external revenues (partner companies, national incentive funds, local authorities and European Union), 49% from the Government and, finally, 21% from two funds dedicated to clean-up of civil and defense facilities. Of the euros 1, 391 M devoted to low-carbon energies, research into the new energy technologies and nuclear systems of the future each received a budget of euros 151 M in 2011. CEA plays a key role in the European Energy Research Alliance, as a founding member, a member of the executive committee and a member of the secretariat. It is France's representative. EERA has launched 13 joint programs, including 6 in 2011. It pools the research efforts of more than 150 institutes and universities, with more than 2, 000 staff employed full-time. CEA is present in 8 programs, with 100 full-time staff, in other words 5% of the total partner commitment. This special issue of 'Defis du CEA' journal deals with the main results of the researches carried out in 2011 at the CEA. Contents: 1 - Facts and figures 2011: Intellectual Property, European Financing, Budget, Nuclear Safety, European Research Programs, International Relations, International Collaboration, Spin-off, Scientific Excellence, Training; 2 - Low-carbon energies: Biofuels, Solar

  13. CEA 2011, a look back at a year of research

    International Nuclear Information System (INIS)

    2011-01-01

    For this year 2011, marked by the Fukushima accident, the goal is improved safety. This is a key issue being addressed by CEA, while at the same time boosting its R and D on low-carbon energies, defense and security, Health technologies, information technologies and very large research Infrastructures. With more than 650 priority patents filed in 2011, CEA maintains its position as the leading French research organization. CEA stands in 4. place among the European research organizations, in terms of the number of projects (535, including 70 that it coordinates) and financing obtained (nearly euros 55 M) under the European Commission's FP7 framework programme. CEA's civil programs are 30% funded from external revenues (partner companies, national incentive funds, local authorities and European Union), 49% from the Government and, finally, 21% from two funds dedicated to clean-up of civil and defense facilities. Of the euros 1, 391 M devoted to low-carbon energies, research into the new energy technologies and nuclear systems of the future each received a budget of euros 151 M in 2011. CEA plays a key role in the European Energy Research Alliance, as a founding member, a member of the executive committee and a member of the secretariat. It is France's representative. EERA has launched 13 joint programs, including 6 in 2011. It pools the research efforts of more than 150 institutes and universities, with more than 2, 000 staff employed full-time. CEA is present in 8 programs, with 100 full-time staff, in other words 5% of the total partner commitment. This special issue of 'Defis du CEA' journal deals with the main results of the researches carried out in 2011 at the CEA. Contents: 1 - Facts and figures 2011: Intellectual Property, European Financing, Budget, Nuclear Safety, European Research Programs, International Relations, International Collaboration, Spin-off, Scientific Excellence, Training; 2 - Low-carbon energies: Biofuels, Solar Photovoltaic, Nuclear, Energy

  14. Study relating to the physico-chemical behaviour of heavy water in nuclear reactors; Etudes relatives au comportement physico-chimique de l'eau lourde dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Chenouard, J.; Dirian, G.; Roth, E.; Vignet, P.; Platzer, R. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1959-07-01

    Chemical and isotope pollution, and radiolytic decomposition are the two most important ways in which heavy water becomes degraded in nuclear reactors. Chemical pollution has led to the creation of ion exchange purification loops specially designed for reactors: the report contains a description in detail of the application of this purification method in CEA research reactors, including the analysis required, results obtained, and their interpretation. The intelligence obtained on radiolytic decomposition with the same facilities is also discussed, as well as the recombination apparatus and control equipment utilized. Finally, investigation to date in the CEA on recombination circuits for power reactors is also discussed. (author) [French] Parmi les degradations subies par l'eau lourde dans les reacteurs nucleaires, les deux plus importantes sont la pollution chimique et isotopique et la decomposition radiolytique. La pollution chimique a conduit a mettre au point pour le cas particulier des reacteurs, des circuits d'epuration par echange d'ions. On decrit ici en detail la mise en oeuvre de cette methode dans les reacteurs de recherche du CEA; les controles qu'elle necessite, les resultats obtenus et leur interpretation. En ce qui concerne la dissociation radiolytique de l'eau, les renseignements obtenus sur ces memes reacteurs sont communiques, ainsi que les details des dispositifs de recombinaison et des moyens de controle. Enfin, on fait le point des etudes poursuivies au CEA sur ces memes problemes de recombinaison dans le cas des reacteurs de puissance. (auteur)

  15. Fuel-cladding interaction. Framatome CEA experiment on pencils preirradiated in nuclear power plants

    International Nuclear Information System (INIS)

    Atabek, Rosemarie; Vignesoult, Nicole

    1979-01-01

    The study of the fuel-cladding interaction is the subject of an important joint research programme between Framatome and the CEA. Tests are performed either on whole fuel rods, not exceeding two metres in length, from BR3 or the CAP (PRISCA experiment) or on fuel rods refabricated in hot cells from fuel rods of power reactors (FABRICE experiment). The first results reveal the two mechanical and chemical aspects of the interaction phenomenon: the permissible power surge of the fuel elements passes through a minimum for an integrated fast dose (E>1MeV) of around 1.5x10 21 n/cm 2 ; a study made with the electronic microprobe and the scanning microscope shows that the Te, I and Cs fission products are the corrosive agents of the cladding [fr

  16. Okulo natural reactors

    International Nuclear Information System (INIS)

    Yamakawa, Minoru

    1993-01-01

    French CEA has reported in 1972 that natural nuclear reactors existed in Okulo uranium deposit in Gabon in Africa, that caused nuclear fission chain reaction (Okulo phenomena) spontaneously two billion years ago. The fission products and transuranic elements produced by the natural reactors have been preserved in strata without movement while subjected to geological phenomena for such very long years. 16 zones of the natural reactors have been discovered so far. The geological features of the Okulo uranium deposit are explained. The total amount of 235 U lost by the chain reaction was estimated to be about 6t, and the fission products were about 6t. The Okulo phenomena offered the valuable results of the synthetic formation disposal test that the nature has carried out for such long years. The significance of the study on natural analog is discussed. Organic substances and the mechanism of holding and movement of uranium and fission nuclides, the stability of uraninite and the age measurement of the deposit by Nd-Sm process are reported as the main results. (K.I.)

  17. The OSIRIS-REx Contamination Control and Witness Strategy

    Science.gov (United States)

    Dworkin, J. P.; Adelman, L.; Ajluni, T. M.; Andronikov, A. V.; Ballou, D. M.; Bartels, A. E.; Beshore, E.; Bierhaus, E. B.; Boynton, W. V.; Brucato, J. R.; hide

    2015-01-01

    The OSIRIS-REx mission (Origins, Spectral Interpretation, Resource Identification, and Security Regolith Explorer) is the third NASA New Frontiers mission. It is scheduled for launch in 2016. The primary objective of the mission is to return at least 60 g of "pristine" material from the B-type near- Earth asteroid (101955) Bennu, which is spectrally similar to organic-rich CI or CM meteorites [1]. The study of these samples will advance our understanding of materials available for the origin of life on Earth or elsewhere. The spacecraft will rendezvous with Bennu in 2018 and spend at least a year characterizing the asteroid before executing a maneuver to recover a sample of regolith in the touch-and-go sample acquisition mechanism (TAGSAM). The TAGSAM and sample is stowed in the sample return capsule (SRC) and returned to Earth in 2023.

  18. Balance 2003 of the risks control at the Cea

    International Nuclear Information System (INIS)

    2004-07-01

    As a research center on the energy, the information and health technologies and the defense, the Cea activities are indissociable from the risk control notion. To organize the risks management, the Cea decided to create in july 2003 a special pole of risks control and management. This presentation is based on some major topics of the risks control: the environmental impact control, the occupational risks control, the installations safety control and the hazardous matter transport control. (A.L.B.)

  19. The Prognostic Significance of Pretreatment Serum CEA Levels in Gastric Cancer: A Meta-Analysis Including 14651 Patients

    Science.gov (United States)

    Deng, Kai; Yang, Li; Hu, Bing; Wu, Hao; Zhu, Hong; Tang, Chengwei

    2015-01-01

    Background Carcinoembryonic antigen (CEA) is commonly used as a serum tumor marker in clinical practice; however, its prognostic value for gastric cancer patients remains uncertain. This meta-analysis was performed to assess the prognostic value of CEA and investigate CEA as a tumor marker. Methods PubMed, EMBASE and other databases were searched for potentially eligible studies. Forty-one studies reporting the prognostic effect of pretreatment serum CEA expression in gastric cancer patients were selected. Data on 14651 eligible patients were retrieved for the meta-analysis. Based on the data extracted from the available literature, the hazard ratio (HR) and 95% confidence interval (CI) for an adverse prognosis were estimated for gastric cancer patients with elevated pretreatment serum levels of CEA (CEA+) relative to patients with normal pretreatment CEA levels (CEA-). Results The CEA+ patients had a significantly poorer prognosis than the CEA- patients in terms of overall survival (OS: HR 1.716, 95% CI 1.594 - 1.848, P 0.05). In the pooled analyses of multivariate-adjusted HRs, the results suggested that pretreatment serum CEA may be an independent prognostic factor in gastric cancer (OS: HR 1.681, 95% CI 1.425 - 1.982; DSS: HR 1.900, 95% CI 1.441 - 2.505; DFS: HR 2.579, 95% CI 1.935 - 3.436). Conclusion/Significance The meta-analysis based on the available literature supported the association of elevated pretreatment serum CEA levels with a poor prognosis for gastric cancer and a nearly doubled risk of mortality in gastric cancer patients. CEA may be an independent prognostic factor for gastric cancer patients and may aid in determining appropriate treatment which may preferentially benefit the CEA+ patients. PMID:25879931

  20. Clinical Significance of Plasma CEA Levels in the Patients with Cervical Carcinoma during Follow-Up

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Sung Beom; Kim, Joo Young; Choi, Myung Sun; Rha, Joong Yeol; Lee, Min Jae [Korea University College of Medicine, Seoul (Korea, Republic of)

    1991-12-15

    Carcinoembryonic antigen (CEA) has been studied in the field of gynecologic malignancy to determine whether it can be used as a tumor marker for early detection of recurrence or evaluation of therapeutic results. From January 1985 through December 1989, a total of 239 cervical cancer patients were entered for an analysis of plasma CEA level in the group with cervical cancer compared to the control group consisting of 65 normal healthy women and 18 women with benign gynecologic disease. Plasma CEA levels appear to be directly related with the tumor extension and as stages advance, the incidence of patients with abnormal plasma CEA levels is increased. Also, there seems to be a little higher incidence of abnormal CEA levels in patients with adenocarcinomas or adenosquamous carcinoma but not statistically significant because of small number of patients. When the patients developed recurrence, plasma CEA levels are markedly elevated in the majority, particularly in patients with hepatic metastases. In conclusion, serial plasma CEA checks could be used to detect recurrence during follow-up after treatment of cervical cancer.

  1. Validation of photon-heating calculations in irradiation reactor with the experimental AMMON program and the CARMEN device

    International Nuclear Information System (INIS)

    Lemaire, Matthieu

    2015-01-01

    TRIPOLI-4 and MCNP codes, using identical nuclear data, were conducted in geometrical configurations of interest for the AMMON experiment and JHR. The objective was to assess the influence of different electromagnetic shower models (electron-transport models mainly) on photon-heating calculations. This study shows a good agreement between the two codes for photon-heating calculations. Secondly, we evaluated the impact of a simplified calculation scheme for photon-heating calculations in the JHR: the discrepancies between a 4-particle-transport calculation (absorbed-dose calculation with charged-particle transport) and a 2-particle-transport (kerma calculation with neutron and photon transport only) were determined in JHR irradiation devices and internal structures. Discrepancies up to 20% were highlighted between kerma and absorbed dose in some structures. This study therefore emphasizes the importance of light-charged-particle transport for JHR photon-heating calculations. The fourth and last part of this work was conducted in collaboration with the IM2NP research team from Aix-Marseille Universite (AMU) in the framework of the LIMMEX joint laboratory. The study consisted in providing calculation/measurement comparisons for a series of heating measurements carried out in January 2012 at the core periphery of OSIRIS material-testing reactor (located in CEA Saclay) with the differential calorimeter of the CARMEN multipurpose device. (author) [fr

  2. The collaboration of Japan and France on the design of ASTRID sodium fast reactor

    International Nuclear Information System (INIS)

    Varaine, Frederic; Rodriguez, Gilles; Hamy, Jean-Marie; Hayafune, Hiroki; Iitsuka, Toru; Mochida, Haruo

    2017-01-01

    Since the beginning (2010), the management of ASTRID project was organized around a strong involvement of industrial partners in the reactor design. The ASTRID project has now entered into its Basic Design phase (duration from year 2016 to 2019) with fourteen industrial partners. Since 2014, a partnership with Japanese nuclear institutes and industries is effective on two main items: ASTRID reactor design studies and R and D in support of Sodium Fast Reactors (SFR). This French-Japanese collaboration on ASTRID Program and Sodium Fast Reactor has been set up in two steps: the signature of a General Arrangement between CEA and the representatives of MEXT and METI on May 5th, 2014; and in a second step, an Implementing Arrangement signed the same year on August 7th by CEA, AREVA NP, JAEA, MHI and MFBR. This collaboration of a significant level is foreseen to run at least up to the end of 2019. At the beginning, the collaborative work (input data, planning and deliverables) was divided in 29 Task Sheets covering ASTRID design (3 Task Sheets) and R and D (26 Tasks Sheets). Since 2016, the contribution of JAEA / MHI-MFBR to the ASTRID reactor engineering studies has significantly raised, passing from 3 to 9 Design Task Sheets. Thus, even if the cooperation is recent, the cooperation between CEA, AREVA NP, JAEA, MHI-MFBR is fruitful and it has been planned by all parties to enlarge Japanese contribution to a process called “Joint Evaluation” to prepare future Joint Design. This paper aims at the overview of the significant involvement of JAEA / MHI-MFBR in the ASTRID design studies through these 9 Task Sheets, covering in particular the design of an active decay heat removal system, and of a passive reactor shutdown system based on a Curie point electromagnet system. MHI / MFBR teams are also implies in fabricability studies of complex component such as the Above Core Structure or the Polar Table. In addition the new Task Sheets are now focusing on thermal

  3. The 'SURA' fast reactor program

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    The Commissariat a l'Energie Atomique's SURA program on fast reactor safety consists of two specific testing programs on fastbreeder reactor safety: the Cabri and Scarabee programs. Both Cabri and Scarabee are examples of multinational research collaboration. The CEA and the Karlsruhe Nuclear Research Center are each covering half of the construction costs. Britain, the US and Japan are also due to participate in these experiments. The aim of the programs is to examine the behaviour of fuel in sodium cooled fast reactors. The Cabri program consists of setting off a reactivity accident in a power reactor core which is cooled with liquid sodium, such an accident occurring after a sharp increase in reactivity or as a result of the pump suddenly breaking down without there at the same time being any fall in the control rods. In 1967 the Commissariat a l'Energie Atomique started its Scarabee research program which is trying to analyse the sort of things that can go wrong with fuel cooling systems and what the consequences can be [fr

  4. Nuclear energy in France. Respective part of CEA, EDF, FRAMATOME

    International Nuclear Information System (INIS)

    Graf, J.J.

    1976-01-01

    In France, the three actors on the nuclear stage are CEA, EDF, and industry. The CEA, important organism of research and development, represents the public power, counsels the Government for safety and constitutes the State interference by the indirect mean of budget which is assigned to it. The industry, FRAMATOME, is commissioned to build plants. EDF has vocation to provide electricity at the lower costs [fr

  5. The current CEA/DRN safety approach for the design and the assessment of future nuclear installations

    International Nuclear Information System (INIS)

    Fiorini, G.L.; Pinto, P.L.; Costa, M.

    1999-01-01

    The purpose of the document is to present the basis of the safety approach currently implemented by the CEA/DRN, both for the design and the assessment of innovative systems and future nuclear installations. This approach is the result of the experience maturated, within the context of the CEA/DRN Innovative Programme through practical applications over several future concepts, both for fission and fusion reactors, as well as for waste disposal. The background of this experience is structured coherently with the European Safety Authorities recommendations and the European Utilities Requirements (EUR). The Defence In Depth principle and its application, by means, among others, of the barrier concept, remains the basis of the safety design process of future nuclear installations. Its adequacy is checked through the safety assessment. The methodology for Lines Of Defence (LOD) implementation as well as the one for the LOD architecture assessment is shown and motivated. The document shows that the clear and unambiguous definition of the safety approach provides an essential base for the organisation of the design tasks, being sure that the safety aspects are correctly taken into account and implemented, and for an adequate safety assessment of the final design, both from qualitative point of view as well as for the quantitative safety analysis. (author)

  6. How to Add Value to your Business with CEA: A Practical Approach

    Directory of Open Access Journals (Sweden)

    Daniel Cardenas

    2010-04-01

    Full Text Available Companies are always trying to differentiate themselves from the rest of the pack by applying different strategies such as improving customer service, increasing the efficiency of their operations, or reducing their costs. Most of the time, however, these goals are competing against each other for scarce resources, and managers often need to decide to concentrate on one. A small company can effectively and simultaneously accomplish these goals for a fraction of the cost by implementing communications-enabled business processes or solutions, which are a set of technology components that add real-time networking functionality to applications. One particular implementation of this framework is the one provided by Coral CEA. Coral CEA is a business ecosystem anchored around CEA functionalities that are offered as building blocks, out-of-the-box components that link the capabilities and intelligence of networks platforms with the power of current applications to provide a new set of features and functionalities. In this article, we show how a small company called Rezact, located in the ski resort town of Mont-Tremblant, Quebec, successfully implemented CEA capabilities within its own operations using Coral CEA services.

  7. Diagnostic test pepsinogen I and combination with tumor marker CEA in gastric cancer

    Science.gov (United States)

    Sembiring, J.; Sarumpaet, K.; Ganie, R. A.

    2018-03-01

    Gastric cancer (GC) is the fifth leading cause of cancer and the third leading cause of cancer-related mortality globally. Human pepsinogens (HP) are considered promising serological biomarkers for the screening of atrophic gastritis (AG) and GC. HP are biochemically and immunochemically classified into two groups: pepsinogen I (PG I) and PG II. Carcinoembryonic antigen (CEA) is a glycoprotein, which is present in normal mucosal cells but increased amounts are associated with adenocarcinoma, especially colorectal cancer. CEA in combination with other tumour markers can be used in pre-operative staging and thereby assist in the planning of the type of surgery required and future management options. The purpose of this study was to diagnose test PG I and combination with tumor marker CEA in 32 patients suspected with GC. There was a significant difference in levels of CEA between GC group with non-GC with a value p <0.001. PGI sensitivity was 70.58% and specificity 93.3%. The sensitivity of PGI and CEA combination of 94.1% and specificity 80%. The area of AUC obtained was 92.7% at 95% confidence interval (82.7-100%). This AUC value indicated that the value of diagnostic accuracy of the PGI and CEA combinations of 92.7%.

  8. Physical protection of nuclear materials and facilities in CEA

    International Nuclear Information System (INIS)

    Garnier-Gratia, M.-H.; Jorda, A.

    2001-01-01

    Full text: CEA (Commissariat a l'Energie Atomique), as nuclear operator, is responsible for the control and protection of their nuclear materials. Inside CEA, DCS (Central Security Division) is in charge of the security matters, DCS defines the CEA strategy in this field, especially in physical protection. The paper will present the physical protection strategy of CEA. DCS defines the rules and methods; the operators have to apply in order to fulfill the security objectives of CEA. CEA has to provide the regulatory authority with documents proving that it is in accordance with the requirements of the 25th July 1980 law and 12th May 1981 decree. It has to implement all the necessary means in order to achieve the results requested by the regulatory authority. All these arrangements are described in the 'license and control file'. This file should specify the facility safeguards and physical protection system. Accounting measures are also described. In this file, the petitioner has to justify its capacity for holding nuclear materials and for exercising authorized activities on them. So the organization and the installed means have to be described in this authorization file. For physical protection, containment, surveillance and physical protection measures are presented: Containment measures must prevent the unauthorized or unjustified movements of nuclear material in the framework of the authorized activities; Surveillance measures must guarantee the integrity of the containment, check that no material is exiting by an abnormal channel; Physical protection measures for the materials, the premises and the facilities are intended to protect them against malevolent actions by means of security systems. The Central Security Division has established guidelines to provide guidance to the nuclear materials holders in writing such files. Each holding unit has to establish a 'license and control file' and each CEA site establishes a 'site license and control file

  9. Odin-OSIRIS stratospheric aerosol data product and SAGE III intercomparison

    Directory of Open Access Journals (Sweden)

    A. E. Bourassa

    2012-01-01

    Full Text Available The scattered sunlight measurements made by the Optical Spectrograph and InfraRed Imaging System (OSIRIS on the Odin spacecraft are used to retrieve vertical profiles of stratospheric aerosol extinction at 750 nm. The recently released OSIRIS Version 5 data product contains the first publicly released stratospheric aerosol extinction retrievals, and these are now available for the entire Odin mission, which extends from the present day back to launch in 2001. A proof-of-concept study for the retrieval of stratospheric aerosol extinction from limb scatter measurements was previously published and the Version 5 data product retrievals are based on this work, but incorporate several important improvements to the algorithm. One of the primary changes is the use of a new retrieval vector that greatly improves the sensitivity to aerosol scattering by incorporating a forward modeled calculation of the radiance from a Rayleigh atmosphere. Additional improvements include a coupled retrieval of the effective albedo, a new method for normalization of the retrieval vector to improve signal-to-noise, and the use of an initial guess that is representative of very low background aerosol loading conditions, which allows for maximal retrieval range. Furthermore, the Version 5 data set is compared to Stratospheric Aerosol and Gas Experiment (SAGE III 755 nm extinction profiles during the almost four years of mission overlap from 2002 to late 2005. The vertical structure in coincident profile measurements is well correlated and the statistics on a relatively large set of tight coincident measurements show agreement between the measurements from the two instruments to within approximately 10% throughout the 15 to 25 km altitude range, which covers the bulk of the stratospheric aerosol layer for the mid and high latitude cases studied here.

  10. Prognostic impact of carcinoembryonic antigen (CEA) on patients with metastatic pancreatic cancer: A retrospective cohort study.

    Science.gov (United States)

    Imaoka, Hiroshi; Mizuno, Nobumasa; Hara, Kazuo; Hijioka, Susumu; Tajika, Masahiro; Tanaka, Tsutomu; Ishihara, Makoto; Hirayama, Yutaka; Hieda, Nobuhiro; Yoshida, Tsukasa; Okuno, Nozomi; Shimizu, Yasuhiro; Niwa, Yasumasa; Yamao, Kenji

    2016-01-01

    Carcinoembryonic antigen (CEA) is one of the most widely used tumor markers, and its level is increased in 30-60% of patients with pancreatic cancer (PC). However, little is known about the implications of CEA as a prognostic marker in metastatic PC. The purpose of this study was to examine the usefulness of CEA levels as a prognostic marker in patients with metastatic PC. We conducted a retrospective cohort study using data from a computerized database. A total of 433 patients with metastatic disease were analyzed. Median overall survival (OS) was significantly shorter for patients with high CEA (>5 ng/ml) than with normal CEA (≤5 ng/ml) (6.8 vs. 10.3 months, respectively; p CEA level was an independent predictive factor for OS (hazard ratio [HR], 1.81; 95% confidence interval [CI], 1.45-2.26). In the high CEA group, OS in patients treated with combination chemotherapy was similar to that with single-agent chemotherapy (median, 7.1 vs. 6.8 months; HR for OS, 0.99; 95% CI, 0.71-1.40). The present results show that CEA level is an independent prognostic factor in patients with metastatic PC. A combination chemotherapy regimen may offer modest survival benefit in patients with high CEA. Copyright © 2016 IAP and EPC. Published by Elsevier B.V. All rights reserved.

  11. Nuclear energy for space: Past CEA activities and ongoing OPUS studies

    International Nuclear Information System (INIS)

    Raepsaet, Xavier; Marion, Denis; Valentian, Dominique

    2006-01-01

    Since the beginning of space activities, solar and nuclear energy have been identified as the only available options for extended missions according to present knowledge. Both types have been used extensively for missions on Earth orbit, interplanetary space and planetary/lunar surface. However, the intensity of solar irradiation decreases with the square of the distance from the Sun. Future scientific and human explorations will take benefits of using a safe in-space nuclear reactor for providing both sufficient electric energy and efficient performance for a space propulsion. The first part of the paper presents a brief status of the different types of nuclear power sources, their characteristics and their field of applications. Previous CEA's projects of space nuclear fission reactors that have been studied in the past will also be discussed; the ERATO project in the 80's (design of a Nuclear Electric Propulsion system of 20 to 200 kWe) and the MAPS project in the 90's (definition of a Nuclear Thermal Propulsion system of 300 MWth for 72 kN of thrust). According to the recent road-maps, CEA decided to maintain a waking state in its spatial nuclear activities by carrying out some conceptual design studies of Nuclear Electric Power systems in the range of 100-500 kWe. The second part of the paper describes the main characteristics of this Optimized Propulsion Unit System (OPUS studies) and its different components. These characteristics, the basic options of the OPUS system that have been selected and the reasons associated to those choices are examined. Especially, the nuclear reactor has been defined considering the possible synergies with the next generation of terrestrial nuclear reactor (International Generation IV Forum). After two successive sets of studies, two different versions of this nuclear system have emerged. The first one is a fast, high-temperature helium cooled reactor, coupled to a direct reheated Brayton cycle. This version is technically the

  12. The pre, post brachytherapy and postoperative CEA serum concentration of 53 rectal cancer patients

    International Nuclear Information System (INIS)

    Nguyen Thanh Danh; Nguyen Kim Luu; Phan Van Dan

    2008-01-01

    CEA serum concentration level of 53 rectal cancer patients was measured at moments pre, post brachytherapy (45 Gy), post surgery one week, 6 months and 12 months. Response to radiation with reduce CEA serum concentration was achieved in 20/53 patients (37,7%), mainly at staging Dukes B, C. Postoperative CEA level of patients significantly decreased, especially in resection group. (author)

  13. Hookah smoking and cancer: carcinoembryonic antigen (CEA) levels in exclusive/ever hookah smokers

    OpenAIRE

    Sajid, Khan Mohammad; Chaouachi, Kamal; Mahmood, Rubaida

    2008-01-01

    Abstract Background We have recently published some work on CEA levels in hookah (also called narghile, shisha elsewhere) and cigarette smokers. Hookah smokers had higher levels of CEA than non-smokers although mean levels were low compared to cigarette smokers. However some of them were also users of other tobacco products (cigarettes, bidis, etc.). Objectives To find serum CEA levels in ever/exclusive hookah smokers, i.e. those who smoked only hookah (no cigarettes, bidis, etc.), prepared b...

  14. Preparation of one-vial reduced anti-CEA kit

    International Nuclear Information System (INIS)

    Hamada, Elena Setuko; Muramoto, Emiko; Shiraishi, Emilia Mayumi; Silva, Licia Maria Britto da; Martins, Heidi Pinto; Silva, Constanca Pagano Goncalves da

    1996-01-01

    A rapid and reliable instant reduced anti-CEA lyophilized kit for labelling with 99m Tc was developed. Each vial contains 0.5 mg of reduced anti-CEA, 40 μg of mendronate (MDP), 2.75 μg stannous fluoride (Sn F 2 ) and 15 μ g p-aminobenzoic acid (PABA). Labeling efficiency and stability were higher than 95% and were determined by instant paper chromatography. Biodistribution studies were performed in normal isogenic BALB/c mice at 4,6 and 24 hours after intravenous administration of the radiolabelled product. The maximum amount of activity was accumulated in the liver followed by intestines and kidneys. (author)

  15. New trends for future reactors. A research and development review

    International Nuclear Information System (INIS)

    Anzieu, P.

    2002-01-01

    Third generation reactors proposed to the market are mostly LWR, pressurized or boiling, with confirmed competitiveness. A special effort to increase the safety level is sensible and should be improved. At least, solutions are studied to better use plutonium. The development of a new generation of NPPs offers opportunity to have another step towards more safety, for example in being fail-safe, and towards a minimization of ultimate waste produced. In this field, CEA dedicates its main effort to the development of a gas cooled reactor and constraint on safety, waste minimization are indicated. At least some examples of progression in the safety level of a plant are shown from an existing one to an hypothetical future reactor

  16. The CEA budget in 1982

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    In 1982, the amount of the CEA budget will be 13.4 billions French Francs. The main characteristics are the priority for employment and investments. In this budget programs are adapted to fit R and D to the government policy: innovation, industrial valorization and fundamental research especially thermonuclear fusion and in the electronuclear field to safety, reprocessing and radioactive waste management [fr

  17. An example of regulating process for an advanced reactor: Creys-Malville

    International Nuclear Information System (INIS)

    Cravero, M.

    1978-01-01

    The general philosophy for the regulatory control of the Super-Phenix fast breeder reactor was the same as for other types of nuclear power plants. The licensing process for both conventional and nuclear aspects was also identical to that for other nuclear units. On the other hand, safety recommendations were especially prepared by the CEA's appropriate services on the basis of acquired experience. The paper analyses the development of the licensing process for the reactor and knowledge to be gained for future units of this type. (NEA) [fr

  18. A new solid phase enzyme immuno assay using a monoclonal antibody for CEA determinations in patients with various carcinomas

    International Nuclear Information System (INIS)

    Staab, H.J.; Glock, S.; Hornung, A.

    1982-01-01

    The clinical validity of carcinoembryonic antigen (CEA) determination with a new solid phase enzyme immuno assay using a monoclonal antibody (EIA-m) in comparison with a common CEA radioimmunoassay with polyclonal antisera (RIA) was investigated for primary diagnosis in 123 patients with various malignancies and in the postoperative followup of 83 patients with gastrointestinal cancers over a period of about one year. The normal range of the new CEA test in which CEA was directly measured without any further extraction, was calculated from the CEA distribution of 147 healthy blood donors and found to be 0-1.5 μg CEA/l. Besides a very fine reproducibility the CEA-m exhibited a pronounced specificity for CEA from patients with colorectal cancers compared with the RIA. Using a cut-off level of >=1.5 μg CEA/l serum with the EIA-m, the test gave a specificity of 76% with a sensitivity of 72% for preoperative serum specimen of 82 patients with colorectal cancers and a control group of 53 patients with nonmalignant gastrointestinal diseases. In this groups of patients the EIA-m was superior to the RIA test which had a sensitivity of 75% at a specificity of 62% using a threshold of >=2.0 μg CEA/l serum. In the followup studies 3 basic tendencies of the CEA time courses well distinguished from each other could be established for both CEA-Tests. Tumor progression, characterized by steadily increasing CEA levels were evident in 20/23 cases with recurrent disease while decreasing or essentially unchanged CEA levels correlated with NED status in the patients. Furthermore 3/23 cases with metastasis in the followup had initial CEA increases indicated by EIA-m, 3-5 months before this increase of the CEA values was evident with the RIA. Transient CEA elevations, not associated with malignant growth, were found less frequently with the new EIA-m compared to the RIA. (orig.) [de

  19. Results of and prospects for studies on molten salt nuclear reactors

    International Nuclear Information System (INIS)

    Hery, M.; Lecocq, A.

    1983-04-01

    This paper reviews the various studies performed in France by the EDF and CEA teams in the field of molten salt nuclear reactors. These studies include graphite moderating systems, feasibility of a 625 MWth core, lead cooling, structural materials, salts tritium diffusion and corrosion. The experience gained allows eventual development prospects of this system to appraised [fr

  20. In-reactor testing of self-powered neutron detectors and miniature fission chambers

    International Nuclear Information System (INIS)

    Duchene, J.; LeMeur, R.; Verdant, R.

    1975-01-01

    The CEA has tested a variety of ''slow'' self-powered neutron detectors with rhodium, silver and vanadium emitters. Currently there are 120 vanadium detectors in the EL4 heavy water reactor. In addition, ''fast'' detectors with cobalt emitters have been tested at Saclay and 50 of these are in reactor. Other studies are concerned with 6 mm diameter miniature fission chambers. Two fast response chambers with argon-nitrogen filling gas became slow during irradiation, but operated to 600 deg C. An argon filled chamber of 4.7 mm diameter, for traversing in core system in pressurized water reactor, has shown satisfactory test results. (author)

  1. Systemic model for the aid for operating of the reactor Siloe

    International Nuclear Information System (INIS)

    Royer, J.C.; Moulin, V.; Monge, F.

    1995-01-01

    The Service of the Reactor Siloe (CEA/DRN/DRE/SRS), fully aware of the abilities and knowledge of his teams in the field of research reactor operating, has undertaken a project of knowledge engineering in this domain. The following aims have been defined: knowledge capitalization for the installation in order to insure its perenniality and valorization, elaboration of a project for the aid of the reactor operators. This article deals with the different actions by the SRS to reach the aims: realization of a technical model for the operation of the Siloe reactor, development of a knowledge-based system for the aid for operating. These actions based on a knowledge engineering methodology, SAGACE, and using industrial tools will lead to an amelioration of the security and the operating of the Siloe reactor. (authors). 13 refs., 7 figs

  2. OsiriX: an open-source software for navigating in multidimensional DICOM images.

    Science.gov (United States)

    Rosset, Antoine; Spadola, Luca; Ratib, Osman

    2004-09-01

    A multidimensional image navigation and display software was designed for display and interpretation of large sets of multidimensional and multimodality images such as combined PET-CT studies. The software is developed in Objective-C on a Macintosh platform under the MacOS X operating system using the GNUstep development environment. It also benefits from the extremely fast and optimized 3D graphic capabilities of the OpenGL graphic standard widely used for computer games optimized for taking advantage of any hardware graphic accelerator boards available. In the design of the software special attention was given to adapt the user interface to the specific and complex tasks of navigating through large sets of image data. An interactive jog-wheel device widely used in the video and movie industry was implemented to allow users to navigate in the different dimensions of an image set much faster than with a traditional mouse or on-screen cursors and sliders. The program can easily be adapted for very specific tasks that require a limited number of functions, by adding and removing tools from the program's toolbar and avoiding an overwhelming number of unnecessary tools and functions. The processing and image rendering tools of the software are based on the open-source libraries ITK and VTK. This ensures that all new developments in image processing that could emerge from other academic institutions using these libraries can be directly ported to the OsiriX program. OsiriX is provided free of charge under the GNU open-source licensing agreement at http://homepage.mac.com/rossetantoine/osirix.

  3. 2nd CEAS Specialist Conference on Guidance, Navigation and Control

    CERN Document Server

    Mulder, Bob; Choukroun, Daniel; Kampen, Erik-Jan; Visser, Coen; Looye, Gertjan

    2013-01-01

    Following the successful 1st CEAS (Council of European Aerospace Societies) Specialist Conference on Guidance, Navigation and Control (CEAS EuroGNC) held in Munich, Germany in 2011, Delft University of Technology happily accepted the invitation of organizing the 2nd  CEAS EuroGNC in Delft, The Netherlands in 2013. The goal of the conference is to promote new advances in aerospace GNC theory and technologies for enhancing safety, survivability, efficiency, performance, autonomy and intelligence of aerospace systems using on-board sensing, computing and systems. A great push for new developments in GNC are the ever higher safety and sustainability requirements in aviation. Impressive progress was made in new research fields such as sensor and actuator fault detection and diagnosis, reconfigurable and fault tolerant flight control, online safe flight envelop prediction and protection, online global aerodynamic model identification, online global optimization and flight upset recovery. All of these challenges de...

  4. List of reports from BMFT, CEA, EPRI, JSTA and USNRC concerning reactor safety research

    International Nuclear Information System (INIS)

    1982-02-01

    This list reviews reports from the Federal Republic of Germany, from France from Japan and from the United States of America concerning special problems in the field of reactor safety research. According to the cooperation in the Gesellschaft fuer Reaktorsicherheit (GRS). The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig.) [de

  5. Thick Films acoustic sensors devoted to MTR environment measurements. Thick Films acoustic sensors devoted to Material Testing Reactor environment measurements

    International Nuclear Information System (INIS)

    Very, F.; Rosenkrantz, E.; Combette, P.; Ferrandis, J.Y.; Fourmentel, D.; Destouches, C.; Villard, J.F.

    2015-01-01

    The development of advanced instrumentation for in-pile experiments in Material Testing Reactor constitutes a main goal for the improvement of the nuclear fuel behavior knowledge. An acoustic method for fission gas release detection was tested with success during a first experiment called REMORA 3 in 2010 and 2011, and the results were used to differentiate helium and fission gas release kinetics under transient operating conditions. This experiment was lead at OSIRIS reactor (CEA Saclay, France). The maximal temperature on the sensor during the irradiation was about 150 deg. C. In this paper we present a thick film transducer produce by screen printing process. The screen printing of piezoelectric offers a wide range of possible applications for the development of acoustic sensors and piezoelectric structure for measurements in high temperature environment. We firstly produced a Lead Zirconate Titanate (PZT) based paste composed of Pz27 powder from Ferroperm, CF7575 glass, and organic solvent ESL 400. Likewise a Bismuth Titanate based paste synthesized in our laboratory was produced. With these inks we produced thick film up to 130 μm by screen printing process. Material properties characterizations of these thick-film resonators are essential for device design and applications. The piezoelectric coefficients d33 and pyro-electric P(T) coefficient are investigated. The highest P(T) and d33 are respectively 80 μC.m -2 .K -1 and 130 μC.N -1 for the PZT transducer -which validates the fabrication process-. In view of the development of this transducer oriented for high temperature and irradiation environment, we investigated the electrical properties of the transducers for different ranges of frequencies and temperature - from 20 Hz up to 40 MHz between 30 and 400 deg. C. We highlight the evolution of the impedance response and piezoelectric parameters of screen printed piezoelectric structures on alumina. Shortly an irradiation will be realized in order to

  6. Thick Films acoustic sensors devoted to MTR environment measurements. Thick Films acoustic sensors devoted to Material Testing Reactor environment measurements

    Energy Technology Data Exchange (ETDEWEB)

    Very, F.; Rosenkrantz, E.; Combette, P.; Ferrandis, J.Y. [University Montpellier, IES, UMR 5214, F-34000, Montpellier (France); CNRS, IES, UMR 5214, F-34000, Montpellier (France); Fourmentel, D.; Destouches, C.; Villard, J.F. [CEA, DEN, Instrumentation Sensors and Dosimetry Laboratory, Cadarache, F-13108 St Paul lez Durance (France)

    2015-07-01

    The development of advanced instrumentation for in-pile experiments in Material Testing Reactor constitutes a main goal for the improvement of the nuclear fuel behavior knowledge. An acoustic method for fission gas release detection was tested with success during a first experiment called REMORA 3 in 2010 and 2011, and the results were used to differentiate helium and fission gas release kinetics under transient operating conditions. This experiment was lead at OSIRIS reactor (CEA Saclay, France). The maximal temperature on the sensor during the irradiation was about 150 deg. C. In this paper we present a thick film transducer produce by screen printing process. The screen printing of piezoelectric offers a wide range of possible applications for the development of acoustic sensors and piezoelectric structure for measurements in high temperature environment. We firstly produced a Lead Zirconate Titanate (PZT) based paste composed of Pz27 powder from Ferroperm, CF7575 glass, and organic solvent ESL 400. Likewise a Bismuth Titanate based paste synthesized in our laboratory was produced. With these inks we produced thick film up to 130 μm by screen printing process. Material properties characterizations of these thick-film resonators are essential for device design and applications. The piezoelectric coefficients d33 and pyro-electric P(T) coefficient are investigated. The highest P(T) and d33 are respectively 80 μC.m{sup -2}.K{sup -1} and 130 μC.N{sup -1} for the PZT transducer -which validates the fabrication process-. In view of the development of this transducer oriented for high temperature and irradiation environment, we investigated the electrical properties of the transducers for different ranges of frequencies and temperature - from 20 Hz up to 40 MHz between 30 and 400 deg. C. We highlight the evolution of the impedance response and piezoelectric parameters of screen printed piezoelectric structures on alumina. Shortly an irradiation will be realized in

  7. Usefulness of analytical CEA doubling time and half-life time for overlooked synchronous metastases in colorectal carcinoma.

    Science.gov (United States)

    Ito, Katsuki; Hibi, Kenji; Ando, Hideyuki; Hidemura, Kazuhiko; Yamazaki, Taiji; Akiyama, Seiji; Nakao, Akimasa

    2002-02-01

    Measurement of carcinoembryonic antigen (CEA) has been widely applied to detect recurrence, especially of colorectal carcinoma. The validity however, is still controversial. We investigated serial changes in CEA values to calculate whether the CEA doubling time and half-life time could predict metastatic progression or prognosis in colorectal carcinoma. Pre- and post-operative serial serum CEA contents were determined in 22 cases of colorectal cancer with or without metastasis. CEA values were determined by enzyme immunoassay (EIA). Patients were assigned depending upon survival time (within vs. more than 18 months after primary resection) for assessment of CEA doubling time. From the gradient of the semi-logarithmic CEA graph, the preoperative doubling time was calculated and the postoperative half-life time was estimated according to the diagnosis of metastases within 2 years after primary resection [metastasis (+) or (-)]. In spite of the effect of curative re-operation of metastatic lesions or of postoperative adjuvant chemotherapy, the CEA doubling time of the groups showed a relation with prognosis (p = 0.045, Student's t-test) when the patients were divided into >18 and time. The CEA half-life time of the groups without overlooked metastases was statistically longer than those with (mean +/- SD 8.01 +/- 2.07 and 4.33 +/- 1.11, respectively, p Clearance (k) showed a significant difference between the groups (p time appeared to be a less independent prognostic factor, whereas prolongation of the CEA half-life time might potentially suggest the existence of overlooked synchronous metastases from colorectal carcinoma.

  8. CEA and AREVA R and D on V/HTR fuel fabrication with the CAPRI experimental manufacturing line

    International Nuclear Information System (INIS)

    Charollais, Francois; Fonquernie, Sophie; Perrais, Christophe; Perez, Marc; Cellier, Francois; Vitali, Marie-Pierre

    2006-01-01

    In the framework of the French V/HTR fuel development and qualification program, the Commissariat a l'Energie Atomique (CEA) and AREVA through its program called ANTARES (Areva New Technology for Advanced Reactor Energy Supply) conduct R and D projects covering the mastering of UO 2 coated particle and fuel compact fabrication technology. To fulfill this task, a review of past knowledge, of existing technologies and a preliminary laboratory scale work program have been conducted with the aim of retrieving the know-how on HTR coated particle and compact manufacture: - The different stages of UO 2 kernel fabrication GSP Sol-Gel process have been reviewed, reproduced and improved; - The experimental conditions for the chemical vapour deposition (CVD) of coatings have been defined on dummy kernels and development of innovative characterization methods has been carried out; - Former CERCA compacting process has been reviewed and updated. In parallel, an experimental manufacturing line for coated particles, named GAIA, and a compacting line based on former CERCA compacting experience have been designed, constructed and are in operation since early 2005 at CEA Cadarache and CERCA Romans, respectively. These two facilities constitute the CAPRI line (CEA and AREVA PRoduction Integrated line). The major objectives of the CAPRI line are: - to recover and validate past knowledge; - to permit the optimisation of reference fabrication processes for kernels and coatings and the investigation of alternative and innovative fuel design (UCO kernel, ZrC coating); - to test alternative compact process options; - to fabricate and characterize fuel required for irradiation and qualification purpose; - to specify needs for the fabrication of representative V/HTR TRISO fuel meeting industrial standards. This paper presents the progress status of the R and D conducted on V/HTR fuel particle and compact manufacture by mid 2005. (authors)

  9. Recapitulative list of the C.E.A. reports published by the French Atomic Energy Commission (n.757-1062, december 1957-december 1958) supplement to C.E.A. reports n. 593 and 756

    International Nuclear Information System (INIS)

    Schmiterlow, C.G.; Cohen, Y.

    1958-01-01

    Recapitulative list of the C.E.A. reports published by the French Atomic Energy Commission. (number 757-1062, december 1957 - december 1958). Supplement to C.E.A. reports number 593 and 756. (author) [fr

  10. Regolith X-Ray Imaging Spectrometer (REXIS) Aboard the OSIRIS-REx Asteroid Sample Return Mission

    Science.gov (United States)

    Masterson, R. A.; Chodas, M.; Bayley, L.; Allen, B.; Hong, J.; Biswas, P.; McMenamin, C.; Stout, K.; Bokhour, E.; Bralower, H.; Carte, D.; Chen, S.; Jones, M.; Kissel, S.; Schmidt, F.; Smith, M.; Sondecker, G.; Lim, L. F.; Lauretta, D. S.; Grindlay, J. E.; Binzel, R. P.

    2018-02-01

    The Regolith X-ray Imaging Spectrometer (REXIS) is the student collaboration experiment proposed and built by an MIT-Harvard team, launched aboard NASA's OSIRIS-REx asteroid sample return mission. REXIS complements the scientific investigations of other OSIRIS-REx instruments by determining the relative abundances of key elements present on the asteroid's surface by measuring the X-ray fluorescence spectrum (stimulated by the natural solar X-ray flux) over the range of energies 0.5 to 7 keV. REXIS consists of two components: a main imaging spectrometer with a coded aperture mask and a separate solar X-ray monitor to account for the Sun's variability. In addition to element abundance ratios (relative to Si) pinpointing the asteroid's most likely meteorite association, REXIS also maps elemental abundance variability across the asteroid's surface using the asteroid's rotation as well as the spacecraft's orbital motion. Image reconstruction at the highest resolution is facilitated by the coded aperture mask. Through this operation, REXIS will be the first application of X-ray coded aperture imaging to planetary surface mapping, making this student-built instrument a pathfinder toward future planetary exploration. To date, 60 students at the undergraduate and graduate levels have been involved with the REXIS project, with the hands-on experience translating to a dozen Master's and Ph.D. theses and other student publications.

  11. [Present conceptions of the C.E.A. concerning] the development of fast neutron reactors in France

    International Nuclear Information System (INIS)

    Vendryes, G.; Gaussens, J.

    1964-01-01

    1 - The position of fast neutron reactors in the French nuclear energy program. In developing a program based on natural uranium, France will have an important stock of plutonium rich in higher isotopes. The existence of this plutonium and of the depleted uranium arising from the same reactors, has, as a logical consequence, the use of both in fast neutron reactors. Justified by this short term interest, the achievement of fast neutron reactors does, moreover, provide for a future necessity. 2 - Description of a fast neutron central power station of 1000 MWe. We indicate the characteristics of a future fast neutron central power station, plutonium fuelled, and sodium cooled. However uncertain these characteristics may be, they constitute a necessary guide in the orientation of our work. 3 - Studies carried out up to the present time. We give an outline of those studies, often very preliminary, which have given the characteristics cited above. The principal technical areas taken up are the following: - Neutronics (critical masses, breeding ratios, enrichments, flattening of the neutron flux, coefficients of reactivity, reactivity changes as a function of irradiation). - Dynamics, control, and safety. - Technology (design of the core and vessel, of the sodium system, and of the fuel handling mechanisms). These technical studies are complemented by economic considerations. The choice of the optimum characteristics is related to the existence of power production programs, and, in these programs, to the existence of plutonium producing thermal reactors. It is shown how, in this context, the existence of plutonium should be taken into account, and, in addition which mechanisms relate the economics of this plutonium to the choice of the most important parameters of the breeder reactors. 4 - Prototype reactor. The interest in an intermediate stage consisting of a reactor of a power level of about 80 MWe is justified. Its essential characteristics are briefly presented

  12. The SCARABEE experimental fast reactor safety programme already completed

    International Nuclear Information System (INIS)

    Schmitt, A.P.; Teague, H.; Heusener, G.

    1979-08-01

    The SCARABEE in-pile experimental programme comprised a series of tests on unirradiated fuel pins, either single or in seven-pin clusters. The main objective was to obtain information on the mode and consequences of fast reactor fuel pin failure in conditions representative of loss of cooling in a LMFBR. The application of such programmes in full scale reactors leads to the great importance of the interpretation of experimental observations. The interpretation of that programme was carried out jointly by CEA, KFK and UKAEA; this international collaboration led to a sharper focusing on essential features to be modelled in experiments and computer codes and to a valuable convergence of views

  13. Economic modeling and parametric studies for OSIRIS - a HIB-driven IFE power plant

    International Nuclear Information System (INIS)

    Meier, W.R.; Bieri, R.L.

    1992-01-01

    Economic modeling and parametric studies for the Osiris HIB-driven inertial fusion energy (IFE) electric power plant have been conducted to determine the most attractive operating point. Cost scaling relationships have been developed and integrated into a cost-performance model of the plant. The figure-of-merit for determining the most attractive design point is the constant-dollar cost of electricity. Results are presented as a function of the driver energy. The sensitivity of the results to variations in the assumed net electric output and target performance is also examined

  14. CEA in activated macrophages. New diagnostic possibilities for tumor markers in early colorectal cancer.

    Science.gov (United States)

    Japink, Dennis; Leers, Mathie P G; Sosef, Meindert N; Nap, Marius

    2009-08-01

    Serum tumor markers show low sensitivity, making them unsuitable for early detection of cancer. Activated macrophages (AM) from peripheral blood can accumulate tumor marker substances and facilitate early detection in prostate cancer. Here it was investigated whether carcinoembryonic antigen (CEA)-containing macrophages (CEACM) can be used to detect colorectal cancer (CRC) at earlier stages than can serum CEA. Peripheral blood was collected from patients with CRC (n=48), inflammatory colorectal disease (n=5) and from healthy controls (n=18). After separating and labeling AM with CD14-APC/CD16-FITC, AM were intracellularly labeled with anti-CEA antibody and flow cytometrically analyzed. Serum CEA and C-reactive protein (CRP) were measured. The fraction-size of CEACM discriminated between controls and CRC patients, irrespective of AJCC stage (AJCC stage I-IV, pCEA values were significantly elevated in AJCC stage II, III and IV (p=0.02, 0.006 and <0.0001, respectively). Combining CEACM with CRP levels separated CRC from inflammatory colorectal disease. CEACM combined with CRP appears to have diagnostic potential in early CRC.

  15. Key issues in european reactor seismic design

    International Nuclear Information System (INIS)

    Cicognani, G.; Martelli, A.

    1984-01-01

    The paper focuses on the main problems which have arisen in FBR design in Europe due to seismic conditions. Its first part, derived from the final report of a CEC-Belgonucleaire study contract, clarifies how ''real'' is the seismic problem for each site. Then, the second and main part deals with the studies carried out in the european countries on the relevant subjects, typical of FBRs or related to specific needs of single FBRs: these studies, for which contributions were provided by ENEA, CEA, NNC and INTERATOM, concern mainly the numerical and experimental analysis of the core, the reactor vessel, the shut-down system and the reactor building of FBRs under construction or in advanced design phase. Attention is also paid to the studies started for future purposes, the feed-backs on the design due to seismic conditions, and the instructions for future reactors

  16. Clinical significance of determination of serum VEGF and CEA levels in patients with colorectal cancer

    International Nuclear Information System (INIS)

    Du Xiaohui; Song Shaobai; Zheng Wei

    2007-01-01

    Objective: To study the applicability of combined determination of serum VEGF and CEA levels in the diagnosis of colorectal cancer as well as the relationship between VEGF level and stage of the disease. Methods: Serum VEGF (with ELISA) and CEA (with RIA) levels serum were detected in 28 patients with colorectal cancer of various stages and 29 controls. Results: The diagnostic positive rate was 53.6% (15/28), 39.3% (11/28), 71.4% (20/28) with CEA, VEGF and combined test for colorectal cancer, respectively. The serum VEGF levels in patients with advance colorectal cancer were significantly higher than those in patients with earlier stages diseases and controls, VEGF levels were positively correlated with CEA levels (P<0.05). Conclusion: Combined detection of the levels of serum VEGF and CEA could improve significantly the diagnostic positive rate in patients with colorectal cancer. (authors)

  17. Reactors licensing: proposal of an integrated quality and environment regulatory structure for nuclear research reactors in Brazil

    International Nuclear Information System (INIS)

    Serra, Reynaldo Cavalcanti

    2014-01-01

    A new integrated regulatory structure based on quality and integrated issues has been proposed to be implemented on the licensing process of nuclear research reactors in Brazil. The study starts with a literature review about the licensing process in several countries, all of them members of the International Atomic Energy Agency. After this phase it is performed a comparative study with the Brazilian licensing process to identify good practices (positive aspects), the gaps on it and to propose an approach of an integrated quality and environmental management system, in order to contribute with a new licensing process scheme in Brazil. The literature review considered the following research nuclear reactors: Jules-Horowitz and OSIRIS (France), Hanaro (Korea), Maples 1 and 2 (Canada), OPAL (Australia), Pallas (Holand), ETRR-2 (Egypt) and IEA-R1 (Brazil). The current nuclear research reactors licensing process in Brazil is conducted by two regulatory bodies: the Brazilian National Nuclear Energy Commission (CNEN) and the Brazilian Institute of Environment and Renewable Natural Resources (IBAMA). CNEN is responsible by nuclear issues, while IBAMA by environmental one. To support the study it was applied a questionnaire and interviews based on the current regulatory structure to four nuclear research reactors in Brazil. Nowadays, the nuclear research reactor’s licensing process, in Brazil, has six phases and the environmental licensing process has three phases. A correlation study among these phases leads to a proposal of a new quality and environmental integrated licensing structure with four harmonized phases, hence reducing potential delays in this process. (author)

  18. SIRIUS 2: A versatile medium power research reactor

    International Nuclear Information System (INIS)

    Rousselle, P.

    1992-01-01

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

  19. 2011 reporting of the risk handling at CEA

    International Nuclear Information System (INIS)

    Anon.

    2012-01-01

    In 2011 CEA reported 100 events to the Authority for Nuclear Safety (ASN). 93 were graded 0 on the INES scale and 7 were graded 1. None of them had a significant impact on the staff health and the environment. 25% of these events concerned delays in the controls of safety equipment. In 2011 CEA had to manage several situations that led to a response of its crisis center: 1) the explosion of an oven belonging to the Socodei-Centraco company situated near the Marcoule Center, 2) the discovery of about 500 grenades from the first world war during digging out works in the Grenoble Center, 3) flooding due to heavy rains in the Cadarache Center, and 4) an intrusion attempt at the Cadarache Center. (A.C.)

  20. CESAR5.3: Isotopic depletion for Research and Testing Reactor decommissioning

    Science.gov (United States)

    Ritter, Guillaume; Eschbach, Romain; Girieud, Richard; Soulard, Maxime

    2018-05-01

    CESAR stands in French for "simplified depletion applied to reprocessing". The current version is now number 5.3 as it started 30 years ago from a long lasting cooperation with ORANO, co-owner of the code with CEA. This computer code can characterize several types of nuclear fuel assemblies, from the most regular PWR power plants to the most unexpected gas cooled and graphite moderated old timer research facility. Each type of fuel can also include numerous ranges of compositions like UOX, MOX, LEU or HEU. Such versatility comes from a broad catalog of cross section libraries, each corresponding to a specific reactor and fuel matrix design. CESAR goes beyond fuel characterization and can also provide an evaluation of structural materials activation. The cross-sections libraries are generated using the most refined assembly or core level transport code calculation schemes (CEA APOLLO2 or ERANOS), based on the European JEFF3.1.1 nuclear data base. Each new CESAR self shielded cross section library benefits all most recent CEA recommendations as for deterministic physics options. Resulting cross sections are organized as a function of burn up and initial fuel enrichment which allows to condensate this costly process into a series of Legendre polynomials. The final outcome is a fast, accurate and compact CESAR cross section library. Each library is fully validated, against a stochastic transport code (CEA TRIPOLI 4) if needed and against a reference depletion code (CEA DARWIN). Using CESAR does not require any of the neutron physics expertise implemented into cross section libraries generation. It is based on top quality nuclear data (JEFF3.1.1 for ˜400 isotopes) and includes up to date Bateman equation solving algorithms. However, defining a CESAR computation case can be very straightforward. Most results are only 3 steps away from any beginner's ambition: Initial composition, in core depletion and pool decay scenario. On top of a simple utilization architecture

  1. CA72-4 e CEA no soro e no lavado peritonial de doentes com câncer gástrico CA72-4 and CEA in serum and peritoneal washing in gastric cancer

    Directory of Open Access Journals (Sweden)

    Sandra MANDORWSKI

    2002-03-01

    Full Text Available Racional - O tratamento e o prognóstico dos pacientes com câncer gástrico dependem, principalmente, do estádio clínico. Os marcadores tumorais séricos e do lavado peritonial podem auxiliar a avaliar o risco de recurrência da doença. Casuística e Métodos - Quarenta pacientes com câncer gástrico (11 estádio I ou II e 29 estádio III ou IV e 24 com doença benigna foram estudados prospectivamente. Todos os doentes foram submetidos a laparotomia. O sangue e o lavado peritonial foram colhidos durante o ato cirúrgico, antes da retirada do tumor, para determinação dos marcadores CEA e CA72-4. Resultados - Vinte e cinco por cento e 47,5% dos pacientes com câncer gástrico apresentam elevação dos níveis séricos de CEA e CA72-4. Através das curvas ROC definiram-se os valores de corte dos marcadores no lavado peritonial. Através destas curvas, observaram-se que 60% e 57,5% apresentavam CEA e CA72-4 elevado, respectivamente no grupo com câncer gástrico. Os valores de CEA e CA72-4 foram maiores nos pacientes estádios III e IV. No lavado peritonial, os níveis de CEA foram maiores nos doentes com tumores T3-4. Os valores de CA72-4 no lavado peritonial diferenciaram o grupo controle do grupo com câncer gástrico. Conclusão - O CA72-4 foi o marcador sérico mais sensível no diagnóstico de câncer gástrico. Entretanto, no lavado peritonial, o marcador mais sensível foi o CEA. Os valores de CEA foram superiores nos tumores que ultrapassam a serosa e inferiores nos tumores que se restringem a mucosa e muscular.Background - The treatment and the prognosis of gastric cancer patients depends mainly on clinical stage. Serum and peritoneal tumoral markers levels can be helpful to evaluate individual risk for recurrence. Aims - To evaluate the sensibility of the tumoral markers in the serum and in the peritoneal washing on diagnosis of gastric cancer. Patients and Methods - Forty patients with adenocarcinoma of the stomach (11 stage I or

  2. Hookah smoking and cancer: carcinoembryonic antigen (CEA levels in exclusive/ever hookah smokers

    Directory of Open Access Journals (Sweden)

    Chaouachi Kamal

    2008-05-01

    Full Text Available Abstract Background We have recently published some work on CEA levels in hookah (also called narghile, shisha elsewhere and cigarette smokers. Hookah smokers had higher levels of CEA than non-smokers although mean levels were low compared to cigarette smokers. However some of them were also users of other tobacco products (cigarettes, bidis, etc.. Objectives To find serum CEA levels in ever/exclusive hookah smokers, i.e. those who smoked only hookah (no cigarettes, bidis, etc., prepared between 1 and 4 times a day with a quantity of up to 120 g of a tobacco-molasses mixture each (i.e. the tobacco weight equivalent of up to 60 cigarettes of 1 g each and consumed in 1 to 8 sessions. Methods Enhanced chemiluminescent immunometric technique was applied to measure CEA levels in serum samples from 59 exclusive male smokers with age ranging from 20–80 years (mean = 58.8 ± 14.7 years and 8–65 years of smoking (mean = 37.7 ± 16.8. 36 non-smokers served as controls. Subjects were divided into 3 groups according to the number of preparations; the number of sessions and the total daily smoking time: Light (1; 1; ≤ 20 minutes; Medium (1–3; 1–3; >20 min to ≤ 2 hrs and Heavy smokers (2–4; 3–8; >2 hrs to ≤ 6 hrs. Because of the nature of distribution of CEA levels among our individuals, Wilcoxon's rank sum two-sample test was applied to compare the variables. Results The overall CEA levels in exclusive hookah smokers (mean: 3.58 ± 2.61 ng/ml; n = 59 were not significantly different (p ≤ 0.0937 from the levels in non-smokers (2.35 ± 0.71 ng/ml. Mean levels in light, medium and heavy smokers were: 1.06 ± 0.492 ng/ml (n = 5; 2.52 ± 1.15 ng/ml (n = 28 and 5.11 ± 3.08 ng/ml (n = 26 respectively. The levels in medium smokers and non-smokers were also not significantly different (p ≤ 0.9138. In heavy smokers, the CEA levels were significantly higher than in non-smokers (p ≤ 0.0001567. Conclusion Overall CEA levels in exclusive hookah

  3. Iodine-131 labeled anti-CEA polyclonal antibody detection of gastrointestinal cancer

    International Nuclear Information System (INIS)

    Nabi, H.A.; Hinkle, G.H.; Olsen, J.O.; Haagensen, D.A.; Thurston, M.O.; Mojzisik, C.; Houchens, D.; Martin, E.W. Jr.

    1984-01-01

    To localize gastrointestinal tumor, 31 patients were injected with 1.7-2.1 mCi I-131 anti-CEA baboon polyclonal antibody. Whole body imaging at 48, 72, and occasionally 96 hrs was performed with a Signa Camera (Technicare) peaked at 364 keV with 20% window. Additional spot views were usually obtained. No subtraction methods were used. All patients had surgical and pathological confirmation of the nuclear medicine studies. Labeled antibody images were positive in 15 (8 recurrent or metastatic colorectal, 2 gastric, 1 pancreatic, 1 primary colon, and 1 breast metastatic to chest wall). In 1, antibody images were positive for metastatic deposits in para-aortic lymph nodes, but negative for primary rectal tumor. True negative images were observed in 6; false negative images in 9 (4 liver metastases, 2 rectal, 1 pancreatic, 1 mesenteric lymph node metastasis, 1 bone metastasis). In all cases, no correlation existed between preoperative CEA serum levels and imaging. I-131 labeled anti-CEA polyclonal antibody imaging proved highly efficient in detecting gastric cancer (2/2) and moderately efficient in detecting recurrent colorectal cancer (8/15). On the other hand, the I-131 labeled polyclonal anti-CEA antibody imaging was of limited value in detecting colon cancer (1/9), pancreatic cancer (1/4) and metastatic liver disease

  4. Research reactor status for future nuclear research in Europe

    Energy Technology Data Exchange (ETDEWEB)

    Raymond, Patrick; Bignan, Gilles; Guidez, Joel [Commissariat a l' Energie Atomique - CEA (France)

    2010-07-01

    Scandinavia). The nuclear renaissance is effective worldwide, with 33 power plants today under construction in the world and a lot of projects in discussion or in preparation in various countries (England, Italy, South Africa, USA...). In Europe, some countries, who phase-out the development nuclear energy, are also coming back in nuclear perspectives as Sweden, Italy, England, Poland,.. All these facts begin to give more work to the MTR (material testing reactors) for testing new materials and new fuels to improve their capacities and their performances. For the ZPR (Zero Power Reactors) test with new fuels allowing additives to suppress Bore utilisation, or allowing to reduce uranium consumption, will be necessary in the near future. For the safety dedicated reactors, test for compliance to last safety requirements are necessary. In this field the refurbishment of the CABRI reactor for Reactivity Insertion Accident studies, is now almost finished for test that should begin in 2010. For the radio isotope production the world demand is increasing year after year, especially for {sup 99}Mo, used in about 70 millions of medicine procedures each year in the world. Today 95% of this world production is assumed by five reactors: HFR (Netherlands), OSIRIS (France), SAFARI (South Africa), BRII (Belgium), and NRU (Canada). The youngest is OSIRIS (41 years) and should be close in 2015. Due to ageing problems NRU and HFR were shut down in 2009 for necessary repair. These points have conduced to some radio isotopes crisis in 2009. This paper explains some projects in line for the future to avoid this type of problems (FRMII initiative, RJH utilisation and PALLAS project). For training activities, needs are huge with nuclear renaissance, especially for the new countries coming back in nuclear field. It will also give a lot of opportunities to low power reactors and to the universities reactors. This paper also provides information on the status of the new projects such as the JHR ongoing

  5. Research reactor status for future nuclear research in Europe

    International Nuclear Information System (INIS)

    Raymond, Patrick; Bignan, Gilles; Guidez, Joel

    2010-01-01

    renaissance is effective worldwide, with 33 power plants today under construction in the world and a lot of projects in discussion or in preparation in various countries (England, Italy, South Africa, USA...). In Europe, some countries, who phase-out the development nuclear energy, are also coming back in nuclear perspectives as Sweden, Italy, England, Poland,.. All these facts begin to give more work to the MTR (material testing reactors) for testing new materials and new fuels to improve their capacities and their performances. For the ZPR (Zero Power Reactors) test with new fuels allowing additives to suppress Bore utilisation, or allowing to reduce uranium consumption, will be necessary in the near future. For the safety dedicated reactors, test for compliance to last safety requirements are necessary. In this field the refurbishment of the CABRI reactor for Reactivity Insertion Accident studies, is now almost finished for test that should begin in 2010. For the radio isotope production the world demand is increasing year after year, especially for 99 Mo, used in about 70 millions of medicine procedures each year in the world. Today 95% of this world production is assumed by five reactors: HFR (Netherlands), OSIRIS (France), SAFARI (South Africa), BRII (Belgium), and NRU (Canada). The youngest is OSIRIS (41 years) and should be close in 2015. Due to ageing problems NRU and HFR were shut down in 2009 for necessary repair. These points have conduced to some radio isotopes crisis in 2009. This paper explains some projects in line for the future to avoid this type of problems (FRMII initiative, RJH utilisation and PALLAS project). For training activities, needs are huge with nuclear renaissance, especially for the new countries coming back in nuclear field. It will also give a lot of opportunities to low power reactors and to the universities reactors. This paper also provides information on the status of the new projects such as the JHR ongoing construction on the Cadarache

  6. CEA: risk management assessment 2011

    International Nuclear Information System (INIS)

    Bigot, Bernard; Bonnevie, Edwige; Maillot, Bernard

    2012-01-01

    This report proposes a qualitative and quantitative overview of CEA activities in the field of risk management during 2011. These activities concerned the impact on the environment, the safety of installations, the management of professional risks (safety and health at work), the radiological protection of workers, the transports of hazardous materials, waste management, protection of sites, installations and heritage, the management of emergency situations, the management of law risks, controls and audits

  7. Annual report of the Association EURATOM/CEA 2003 (executive summary)

    International Nuclear Information System (INIS)

    2003-01-01

    3 different materials (copper base, stainless steel and mono-crystalline molybdenum) have been selected for mirrors used in diagnostic purposes. A new diagnostic for thermographic analysis has been developed for JET. The EURATOM-Cea association is involved in the development of the first ITER neutral beam injector (in particular the source and the accelerator) and in the design of the ITER neutral beam test facility. The EURATOM-Cea association has contributed to the design of an ITER-relevant ICRH launcher that will be installed on JET during the 2004 shutdown. The development of an industrial cutting and welding laser tool for fabrication and maintenance of hydraulic connector parts of the ITER blanket module has been achieved in 2003. Work on the manufacture of the ITER primary first wall panel by HIP forming is ongoing. In the field 'plasma facing components' activities have focused on flat tile technology and particularly on the possibility of failure in cascade of these tiles. A full-scale prototype mock-up of the ITER divertor vertical target has been high flux tested. The hot isostatic pressing technique has been selected for the fabrication of lot of fusion reactor components. Concerning remote handling activities, the feasibility studies for the remote maintenance (cutting, welding and inspection) of the ITER divertor cooling pipe with bore tools have been achieved. In the field 'magnet', activities have focused on an extensive characterization of 3 types of NbTi strand candidate for ITER PF coils and on the thermohydraulic properties of cable-in-conduit conductors. The helium cooled lithium lead (HCLL) breeding blanket concept has been developed for the test blanket module. In the field 'structural materials', work has been dedicated to the development of reduced activation ferritic martensitic steel and of SiC-SiC ceramic composites and of tungsten alloys. In the framework of fusion waste management, different processes that could be used for tritium

  8. CEA A BIOCHEMICAL MARKER FOR DIAGNOSIS AND PROGNOSIS OF GASTROINTESTINAL CANCER

    OpenAIRE

    Prathibha; Vishnu Datt

    2016-01-01

    Serum tumor markers (TM) are widely used for diagnosis and monitoring of treatment of cancer. Carcinoembryonic Antigen (CEA) is one of the most widely investigated tumor markers in gastrointestinal (GI) cancers. Estimation of circulating tumor markers is a non- invasive quantitative method. Serum levels of CEA were studied for diagnosis and prognosis of gastrointestinal malignancies. 140 subjects were undertaken out of which 35 normal and remaining 105 were GI cancer patients. Ser...

  9. OSIRIS, an entirely in-house developed drug discovery informatics system.

    Science.gov (United States)

    Sander, Thomas; Freyss, Joel; von Korff, Modest; Reich, Jacqueline Renée; Rufener, Christian

    2009-02-01

    We present OSIRIS, an entirely in-house developed drug discovery informatics system. Its components cover all information handling aspects from compound synthesis via biological testing to preclinical development. Its design principles are platform and vendor independence, a consistent look and feel, and complete coverage of the drug discovery process by custom tailored applications. These include electronic laboratory notebook applications for biology and chemistry, tools for high-throughput and secondary screening evaluation, chemistry-aware data visualization, physicochemical property prediction, 3D-pharmacophore comparisons, interactive modeling, computing grid based ligand-protein docking, and more. Most applications are developed in Java and are built on top of a Java library layer that provides reusable cheminformatics functionality and GUI components such as chemical editors, structure canonicalization, substructure search, combinatorial enumeration, enhanced stereo perception, force field minimization, and conformation generation.

  10. The French UMo group contribution to new LEU fuel development

    International Nuclear Information System (INIS)

    Hamy, J.M.; Lemoine, P.; Huet, F.; Jarousse, C.; Emin, J.L.

    2005-01-01

    The French UMo Group was based on a close collaboration between CEA and AREVA's companies strongly involved in the MTR field. The aim of this program was to deliver industrially a high performance LEU UMo fuel able to be reprocessed, and suitable for a wide range of Research Reactor, covering the expected needs for MTR next generation. Since 1999, the program has been focused on industrial aspects with the intention to deal with the whole fuel cycle: manufacturing, irradiation behaviour, fuel characterisation, code development and reprocessing validation. It has been based on the fabrication of full-sized U-7%Mo fuel plates with a density up to 8 gU/cm 3 . The dedicated and advanced R and D means provided by the CEA have been used intensively with the contribution of HFR and BR2 facilities in Europe. This paper presents a synthesis of the program and the corresponding significant results obtained. These results have played a major role as regards the UMo dispersion fuel qualification route by issuing, for the first time, evidence of severe performance limitations. Consequently, the global international effort to develop and qualify a high density LEU UMo fuel has been definitively re-routed and forced to overcome these discrepancies by exploring new technical solutions. A French extended program sustained by a CEA and CERCA collaboration has been launched in 2004 in order to develop a suitable UMo fuel solution. UMo dispersion and monolithic fuel are both investigated through three new full-sized plate irradiations planned in OSIRIS. (author)

  11. Nuclear detectors for in-core power-reactors

    International Nuclear Information System (INIS)

    Duchene, Jean; Verdant, Robert.

    1979-12-01

    Nuclear reactor control is commonly obtained through neutronic measurements, ex-core and in-core. In large size reactors flux instabilities may take place. For a good monitoring of them, local in-core power measurements become particularly useful. This paper intends to review the questions about neutronic sensors with could be used in-core. A historical account about methods is given first, from early power reactors with brief description of each system. Sensors presently used (ionization fission chambers, self-powered detectors) are then considered and also those which could be developped such as gamma thermometers. Their physical basis, main characteristics and operation modes are detailed. Preliminary tests and works needed for an extension of their life-time are indicated. As an example present irradiation tests at the CEA are then proposed. Two tables will help comparing the characteristics of each type in terms of its precise purpose: fuel monitoring, safety or power control. Finally a table summarizes the kind of sensors mounted on working power reactors and another one is a review of characteristics for some detectors from obtainable commercial sheets [fr

  12. OSIRIS-REx Flight Dynamics and Navigation Design

    Science.gov (United States)

    Williams, B.; Antreasian, P.; Carranza, E.; Jackman, C.; Leonard, J.; Nelson, D.; Page, B.; Stanbridge, D.; Wibben, D.; Williams, K.; Moreau, M.; Berry, K.; Getzandanner, K.; Liounis, A.; Mashiku, A.; Highsmith, D.; Sutter, B.; Lauretta, D. S.

    2018-06-01

    OSIRIS-REx is the first NASA mission to return a sample of an asteroid to Earth. Navigation and flight dynamics for the mission to acquire and return a sample of asteroid 101955 Bennu establish many firsts for space exploration. These include relatively small orbital maneuvers that are precise to ˜1 mm/s, close-up operations in a captured orbit about an asteroid that is small in size and mass, and planning and orbit phasing to revisit the same spot on Bennu in similar lighting conditions. After preliminary surveys and close approach flyovers of Bennu, the sample site will be scientifically characterized and selected. A robotic shock-absorbing arm with an attached sample collection head mounted on the main spacecraft bus acquires the sample, requiring navigation to Bennu's surface. A touch-and-go sample acquisition maneuver will result in the retrieval of at least 60 grams of regolith, and up to several kilograms. The flight activity concludes with a return cruise to Earth and delivery of the sample return capsule (SRC) for landing and sample recovery at the Utah Test and Training Range (UTTR).

  13. CEA and CA 19-9 are still valuable markers for the prognosis of colorectal and gastric cancer patients.

    Science.gov (United States)

    Sisik, Abdullah; Kaya, Mustafa; Bas, Gurhan; Basak, Fatih; Alimoglu, Orhan

    2013-01-01

    The purpose of this study was to assess the predictive effect of preoperative CEA and CA 19-9 levels on the prognosis of colorectal and gastric cancer patients. CEA and CA 19-9 were evaluated preoperatively in patients undergoing surgery for colorectal cancer (n=116) and gastric cancer (n=49). Patients with CEA levels CEA Group 1, 5-30 ng/mL as CEA Group 2 and >30 ng/ mL were classified as CEA Group 3. Similarly the patients with a CA 19-9 level 100 U/mL as Group and 3. TNM stages and histologic grades were noted according to histopathological reports. Patients with a TNM grade 0 or 1 were classified as Group A, TNM grade 2 patients constituted Group B and TNM grade 3 and 4 patients constituted Group C. Demographic characteristics, tumor locations and blood types of the patients were all recorded and these data were compared with the preoperative CEA and CA19-9 values. A significant correlation between CA 19-9 levels (>100 U/mL) and TNM stage (in advanced stages) was determined. We also determined a significant correlation between TNM stages and positive vlaues for both CEA and CA 19-9 in colorectal and gastric cancer patients. In comparison between CEA and CA 19-9 levels and age, gender, tumor location, ABO blood group, and tumor histologic grade, no significant correlation was found. Positive levels of both CEA and CA 19-9 can be considered to indicate an advanced stage in colorectal and gastric cancer patients.

  14. La construcción de la identidad del rey y los orígenes de su identificación con Osiris

    Directory of Open Access Journals (Sweden)

    María Martha Sarmiento

    2010-04-01

    Full Text Available Para la sociedad del Antiguo Egipto el mito era la forma de legitimación y la explicación de porqué el mundo adquiría determinada forma y orden. El paso de una economía cazadora- recolectora a una propiamente agrícola provoca un cambio de mentalidad en donde la figura del rey aparece como garante del orden dado. En este trabajo analizaremos la construcción de la identidad del rey en el Antiguo Egipto en base a dos interrogantes: los orígenes topográficos del culto a Osiris y cómo a través del mito se produce la identificación de Osiris el rey-padre muerto con su sucesor Horus-rey-hijo-vivo, todo esto vinculado a la formación del Estado

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1955-07-01

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

  16. Establishment of a rationalized safety assurance logic aiming at FBRs with enhanced social acceptance (1). Interim report of CEA/JNC collaboration NWP-5(a) from 1999 to 2001: common view and JNC's contribution

    International Nuclear Information System (INIS)

    Niwa, Hajime; Tobita, Yoshiharu; Kurisaka, Kenichi; Kubo, Shigenobu; Kamiyama, Kenji

    2001-12-01

    This is an interim report describing the progress and the results of the collaborative research works between JNC and CEA on the safety logic in future fast reactors under the title of 'Establishment of a Rationalized Safety Assurance Logic Aiming at FBRs with Enhanced Social Acceptance' from 1999 to 2001. This contains JNC's contribution and common view of both partners. (1) Safety goals are proposed from JNC and CEA. Significant coherency is found such as to keep defense-in depth concept, mitigation measures against core melt are taken into account for containment design, evacuation free' concept is pursued, quantitative safety target is also considered as well as deterministic approach, and improvement of social acceptance is considered from the development stage of the fuel cycle including nuclear power plants. (2) Safety characteristics of each candidate coolant were compared and discussed. Gas-cooled fast reactor is a common interest area. Discussions are focused on: safety design requirements, safety evaluation events list, transient behavior analysis, core catcher designs, and so on. (3) JNC's results include criticality map for predicting CDA behavior and consequences, and CDA analysis results of lead-cooled and gas-cooled fast reactors with SIMMER-III. The collaboration on the action NWP-5a is recognized as being of great importance for the orientation of the innovative design studies. (author)

  17. Uropathogenic E. coli Exploit CEA to Promote Colonization of the Urogenital Tract Mucosa

    Science.gov (United States)

    Muenzner, Petra; Kengmo Tchoupa, Arnaud; Klauser, Benedikt; Brunner, Thomas; Putze, Johannes; Dobrindt, Ulrich; Hauck, Christof R.

    2016-01-01

    Attachment to the host mucosa is a key step in bacterial pathogenesis. On the apical surface of epithelial cells, members of the human carcinoembryonic antigen (CEA) family are abundant glycoproteins involved in cell-cell adhesion and modulation of cell signaling. Interestingly, several gram-negative bacterial pathogens target these receptors by specialized adhesins. The prototype of a CEACAM-binding pathogen, Neisseria gonorrhoeae, utilizes colony opacity associated (Opa) proteins to engage CEA, as well as the CEA-related cell adhesion molecules CEACAM1 and CEACAM6 on human epithelial cells. By heterologous expression of neisserial Opa proteins in non-pathogenic E. coli we find that the Opa protein-CEA interaction is sufficient to alter gene expression, to increase integrin activity and to promote matrix adhesion of infected cervical carcinoma cells and immortalized vaginal epithelial cells in vitro. These CEA-triggered events translate in suppression of exfoliation and improved colonization of the urogenital tract by Opa protein-expressing E. coli in CEA-transgenic compared to wildtype mice. Interestingly, uropathogenic E. coli expressing an unrelated CEACAM-binding protein of the Afa/Dr adhesin family recapitulate the in vitro and in vivo phenotype. In contrast, an isogenic strain lacking the CEACAM-binding adhesin shows reduced colonization and does not suppress epithelial exfoliation. These results demonstrate that engagement of human CEACAMs by distinct bacterial adhesins is sufficient to blunt exfoliation and to promote host infection. Our findings provide novel insight into mucosal colonization by a common UPEC pathotype and help to explain why human CEACAMs are a preferred epithelial target structure for diverse gram-negative bacteria to establish a foothold on the human mucosa. PMID:27171273

  18. Recuperation of the energy released in the G-1, an air-cooled graphite reactor core

    International Nuclear Information System (INIS)

    Chambadal, P.; Pascal, M.

    1955-01-01

    The CEA (in his five-year setting plan) has objective among others, the realization of the two first french reactors moderated with graphite. The construction of the G-1 reactor in Marcoule, first french plutonic core, is achieved so that it will diverge in the beginning of 1956 and reach its full power in the beginning of the second semester of the same year. In this report we will detail the specificities of the reactor and in particular its cooling and energy recuperation system. The G-1 reactor being essentially intended to allow the french technicians to study the behavior of an energy installation supply taking its heat in a nuclear source as early as possible. (M.B.) [fr

  19. Feasibility of reactivity worth measurements by perturbation method with Caliban and Silene experimental reactors

    Energy Technology Data Exchange (ETDEWEB)

    Casoli, Pierre; Authier, Nicolas [Commissariat a l' Energie Atomique, Centre d' Etudes de Valduc, 21120 Is-Sur-Tille (France)

    2008-07-01

    Reactivity worth measurements of material samples put in the central cavities of nuclear reactors allow to test cross section nuclear databases or to extract information about the critical masses of fissile elements. Such experiments have already been completed on the Caliban and Silene experimental reactors operated by the Criticality and Neutronics Research Laboratory of Valduc (CEA, France) using the perturbation measurement technique. Calculations have been performed to prepare future experiments on new materials, such as light elements, structure materials, fission products or actinides. (authors)

  20. Progress report - list of reports from BMFT, CEA, EPRI, JSTA and USNRC reactor safety research

    International Nuclear Information System (INIS)

    1982-10-01

    This list reviews reports from the Federal Republic of Germany, from France, from Japan and from the United States of America concerning special problems in the field of reactor safety research. The list pursues the following order: Country of origin, problem area concerned, according to the Reactor Safety Research Programm of the BMFT, reporting organization. The list of reports appears quarterly. (orig./HP) [de

  1. Development and application of modeling tools for sodium fast reactor inspection

    Energy Technology Data Exchange (ETDEWEB)

    Le Bourdais, Florian; Marchand, Benoît; Baronian, Vahan [CEA LIST, Centre de Saclay F-91191 Gif-sur-Yvette (France)

    2014-02-18

    To support the development of in-service inspection methods for the Advanced Sodium Test Reactor for Industrial Demonstration (ASTRID) project led by the French Atomic Energy Commission (CEA), several tools that allow situations specific to Sodium cooled Fast Reactors (SFR) to be modeled have been implemented in the CIVA software and exploited. This paper details specific applications and results obtained. For instance, a new specular reflection model allows the calculation of complex echoes from scattering structures inside the reactor vessel. EMAT transducer simulation models have been implemented to develop new transducers for sodium visualization and imaging. Guided wave analysis tools have been developed to permit defect detection in the vessel shell. Application examples and comparisons with experimental data are presented.

  2. Clinical significance of determination of serum SA, CEA and CRP levels in patients with colo-rectal cancer

    International Nuclear Information System (INIS)

    Cai Jie; Hu Junyan; Sun Shuming; Cheng Benkun

    2007-01-01

    Objective: To investigate the clinical usefulness of determination of serum SA, CEA and CRP levels in patients with colorectal cancer. Methods: Serum SA (with colorimetry), CEA (with CLIA) and CRP (with ILIA) levels were measured in 120 patients with colo-rectal cancer. Results: (1) Serum SA, CEA and CRP levels increased significantly as the disease stage advanced from Duke A through Duke D. (2) As the malignancy of the growth advanced from well-differentiated to anaplastic, the serum SA and CRP levels increased significantly while the reverse was true for serum CEA levels. (3) In 68 post-operative patients followed 1-5 years, the serum levels of SA, CEA and CRP were significantly higher in the patients with recurrence (n=29) than those in patients without recurrence (n=39) (P<0.01). Conclusion: Serum SA CEA and CRP levels were closely related to the disease process in patients with colo-rectal cancer. (authors)

  3. Annual report of the Association EURATOM/Cea

    International Nuclear Information System (INIS)

    Magaud, Ph.; Le Vagueres, F.

    2002-01-01

    This annual report presents research activities, which have been performed in 2002 by the French EURATOM-Cea association in the frame of the European technology program. The first section describes EFDA (European fusion development agreement) activities and related developments carried out by the association. The second one is dedicated to the underlying technology program and finally the third one presents the inertial confinement fusion activities. In each section the tasks are sorted out according to the EFDA main fields: physics (heating and current drive, remote participation, diagnostics), vessel/in-vessel (vessel/blanket, plasma facing components, remote handling), magnet, tritium breeding and materials (water cooled lithium lead blanket, helium cooled pebble bed blanket, helium cooled lithium lead blanket, reduced activation ferritic martensitic steels, advanced materials, neutron source, fuel cycle), safety and environment, system studies (power plant conceptual studies, socio-economic studies) and JET technology activities. The EURATOM-Cea association is involved in all these studies

  4. Annual report of the Association EURATOM/Cea

    Energy Technology Data Exchange (ETDEWEB)

    Magaud, Ph; Le Vagueres, F

    2002-07-01

    This annual report presents research activities, which have been performed in 2002 by the French EURATOM-Cea association in the frame of the European technology program. The first section describes EFDA (European fusion development agreement) activities and related developments carried out by the association. The second one is dedicated to the underlying technology program and finally the third one presents the inertial confinement fusion activities. In each section the tasks are sorted out according to the EFDA main fields: physics (heating and current drive, remote participation, diagnostics), vessel/in-vessel (vessel/blanket, plasma facing components, remote handling), magnet, tritium breeding and materials (water cooled lithium lead blanket, helium cooled pebble bed blanket, helium cooled lithium lead blanket, reduced activation ferritic martensitic steels, advanced materials, neutron source, fuel cycle), safety and environment, system studies (power plant conceptual studies, socio-economic studies) and JET technology activities. The EURATOM-Cea association is involved in all these studies.

  5. Radioiodination of monoclonal antibody intact anti-CEA

    International Nuclear Information System (INIS)

    Okada, H.; Souza, I.T.T.; Silva, C.P.G.

    1990-11-01

    The purpose of this study is to examine a convenient system that can be used to iodinate monoclonal antibodies which is rapid, simple, efficient and reproducible, and which can be accomplished in radiopharmaceutical laboratories. It is important to remember that antibodies are sensitive biochemicals, subject to losses of the activity that is essential to their mode of action, namely the ability to bind specific antigen. The advent of solid phase iodination agents has greatly expanded the range of gentle iodination techniques available for iodinating sensitive biological materials. The agent most widely used is the Iodogen (1,3,4,6 tetrachloro-3a-6a diphenylglycoluril) method. Anti-CEA 4C sub(11) IgG sub(2a,k) (prepared in the Ludwig Institute-Sao Paulo-Brazil ) is used as model to evaluate the Iodogen methodology. The miniature chromatographic system, also rapid, accurate, simple, efficient was elaborated to determine the labelling efficiency incorporation of iodine into immunoglobulin, and the radiochemical purity of sup(131)I-anti-CEA. (author)

  6. Summary 1998. Releases control and environment monitoring for the CEA Centers

    International Nuclear Information System (INIS)

    1998-01-01

    In the framework of its environmental policy, the CEA aims at reduce as weak as possible, in regards to the technological and economic needs, its activities impacts on the people and the environment. This paper contributes to the public information on the radioactive gaseous and liquid releases during the year 1998. It presents data on the releases and the radioactivity levels around the CEA sites and gathers the associated regulation and monitoring methods. (A.L.B.)

  7. 2010 Criticality Accident Alarm System Benchmark Experiments At The CEA Valduc SILENE Facility

    International Nuclear Information System (INIS)

    Miller, Thomas Martin; Dunn, Michael E.; Wagner, John C.; McMahan, Kimberly L.; Authier, Nicolas; Jacquet, Xavier; Rousseau, Guillaume; Wolff, Herve; Piot, Jerome; Savanier, Laurence; Baclet, Nathalie; Lee, Yi-kang; Masse, Veronique; Trama, Jean-Christophe; Gagnier, Emmanuel; Naury, Sylvie; Lenain, Richard; Hunter, Richard; Kim, Soon; Dulik, George Michael; Reynolds, Kevin H.

    2011-01-01

    Several experiments were performed at the CEA Valduc SILENE reactor facility, which are intended to be published as evaluated benchmark experiments in the ICSBEP Handbook. These evaluated benchmarks will be useful for the verification and validation of radiation transport codes and evaluated nuclear data, particularly those that are used in the analysis of CAASs. During these experiments SILENE was operated in pulsed mode in order to be representative of a criticality accident, which is rare among shielding benchmarks. Measurements of the neutron flux were made with neutron activation foils and measurements of photon doses were made with TLDs. Also unique to these experiments was the presence of several detectors used in actual CAASs, which allowed for the observation of their behavior during an actual critical pulse. This paper presents the preliminary measurement data currently available from these experiments. Also presented are comparisons of preliminary computational results with Scale and TRIPOLI-4 to the preliminary measurement data.

  8. The development of fast reactors in France

    International Nuclear Information System (INIS)

    Vautrey, L.

    1982-01-01

    Only minor changes were introduced in the French nuclear programme by the new government in 1981. The operating conditions of Rapsodie were very satisfactory up to January 1982. After a leak in the double primary jacket (nitrogen circuit) the reactor was shut down for investigations. Phenix is continuing to operate smoothly. Construction of Super Phenix (Creys Malville power plant) is proceeding normally though with some delay. The studies for the future (after Creys Malville) are following their way both for the Project 1500 (Super Phenix 2) and for the specific plants of the fuel cycle. Research and development are largely directed toward Super Phenix 1 needs and the prospects of Super Phenix 2. International cooperation remains very intensive. The financial resources devoted to the development of fast reactors are globally stable. Including fuel cycle and safety (but excluding the Phenix operation) about 1300 millions of francs will be devoted to fast reactors by the C.E.A. in 1982. (author)

  9. The future Jules Horowitz material testing reactor: An opportunity for developing international collaborations on a major European irradiation infrastructure

    International Nuclear Information System (INIS)

    Parrat, D.; Bignan, G.; Maugard, B.; Gonnier, C.; Blandin, C.

    2015-01-01

    Development process of a fuel product or a nuclear material before using at an industrial scale in a power reactor ranges from characterization of the material itself under neutronic flux up to its qualification in accidental conditions. Irradiations in Material Testing Reactors (MTRs) are in practice the basis of the whole process, in complement of prediction capabilities gained by modelling. Dedicated experimental reactors play also an important complementary role for some specific integral tests (e.g. RIA tests). Irradiations of precursors in power reactors are often limited to products which present a slight design evolution compare to the standard product or are implemented for further tests when a statistical approach is useful for defining a safety criterion. However European MTR park status is characterized by ageing infrastructures, which could cause operational issues in coming years, either on technological or on safety point of views. Moreover some specific supplies related to the public demand could be strongly affected (e.g. radiopharmaceutical targets). To avoid a lack in irradiation capacity offer at European level, CEA launched the Jules Horowitz Material Testing Reactor (JHR) international program, in the frame of a Consortium gathering also EDF (FR), AREVA (FR), European Commission (EU), SCK.CEN (BE), VTT (FI), CIEMAT (SP), STUDSVIK (SE), UJV (CZ), NNL (UK), IAEC (IL), DAE (IN) and as associated partnership: JAEA (JP). Some institutions in this list are themselves the flagship of a national Consortium. Discussions for enlarging participation are on-going with other countries, as JHR Consortium is open to new member entrance until JHR completion. The Jules Horowitz Material Testing Reactor (JHR MTR) is under construction at CEA Cadarache in southern France and will be an important international User Facility for R&D in support to the nuclear industry, research centres, regulatory bodies and TSO, and academic institutions. It represents a unique

  10. Eddy current testing of PWR fuel pencils in the pool of the Osiris reactor

    International Nuclear Information System (INIS)

    Faure, M.; Marchand, L.

    1983-12-01

    A nondestructive testing bench is described. It is devoted to examination of high residual power fuel pencils without stress on the cladding nor interference with cooling. Guiding by fluid bearings decrease the background noise. Scanning speed is limited only by safety criteria and data acquisition configuration. Simultaneous control of various parameters is possible. Associated to an irradiation loop, loaded and unloaded in a reactor swinning pool, this bench can follow fuel pencil degradation after each irradiation cycle [fr

  11. Importance of Sodium Fuel Interaction in Fast Reactor Safety Evaluation - CEA Point of View

    International Nuclear Information System (INIS)

    Tanguy, P.

    1976-01-01

    The consequences of interactions between molten metal (aluminium-uranium alloy) and water have long been a subject of concern for those in charge of reactor safety, following accidents observed or induced in certain reactors (BORAX, SL1, SPERT 1 D). In such accidents, as in similar cases occurring in traditional industries (aluminium foundries, steel works, paper mills...) the contact between the hot liquid product and the coolant entails rapid vaporization of the latter with effects identical to that of an explosive. Although chemical reactions of water decomposition occur in some cases, the main phenomenon is the conversion of the thermal energy stored in the hot substance into mechanical energy. Despite the fact that a molten oxide fuel differs from an aluminium-uranium alloy, as does sodium from water, the consequences of possible contact between the molten mixed uranium and plutonium oxide and sodium must be carefully studied since such a contact may occur in accident conditions in sodium-cooled fast neutron reactors. The essential purpose of an evaluation of reactor safety in accident conditions is in fact to ensure the containment of dangerous products Consequently, any phenomenon likely to endanger containment barriers must be carefully examined. In conclusion: Whereas an accident within an assembly seems to show little likelihood of creating conditions seriously endangering fuel containment, the gravity of problems associated with an overall accident on the core is worthy of thorough and attentive study. In the case of an overall accident on the core of a fast reactor, the interaction between the molten fuel and the sodium is of consequence at two levels. The first is the retention of mechanical energy which may be considerable. The second is the recovery of fuel fragments in an overall cooled configuration but where local cooling problems may give rise to interaction. A greater effort is required in performing tests and mastering their results to

  12. Comparison of Ablation Predictions for Carbonaceous Materials Using CEA and JANAF-Based Species Thermodynamics

    Science.gov (United States)

    Milos, Frank S.

    2011-01-01

    In most previous work at NASA Ames Research Center, ablation predictions for carbonaceous materials were obtained using a species thermodynamics database developed by Aerotherm Corporation. This database is derived mostly from the JANAF thermochemical tables. However, the CEA thermodynamics database, also used by NASA, is considered more up to date. In this work, the FIAT code was modified to use CEA-based curve fits for species thermodynamics, then analyses using both the JANAF and CEA thermodynamics were performed for carbon and carbon phenolic materials over a range of test conditions. The ablation predictions are comparable at lower heat fluxes where the dominant mechanism is carbon oxidation. However, the predictions begin to diverge in the sublimation regime, with the CEA model predicting lower recession. The disagreement is more significant for carbon phenolic than for carbon, and this difference is attributed to hydrocarbon species that may contribute to the ablation rate.

  13. Cliffs versus plains: Can ROSINA/COPS and OSIRIS data of comet 67P/Churyumov-Gerasimenko in autumn 2014 constrain inhomogeneous outgassing?

    Science.gov (United States)

    Marschall, R.; Mottola, S.; Su, C. C.; Liao, Y.; Rubin, M.; Wu, J. S.; Thomas, N.; Altwegg, K.; Sierks, H.; Ip, W.-H.; Keller, H. U.; Knollenberg, J.; Kührt, E.; Lai, I. L.; Skorov, Y.; Jorda, L.; Preusker, F.; Scholten, F.; Vincent, J.-B.; Osiris Team; Rosina Team

    2017-09-01

    Context. This paper describes the modelling of gas and dust data acquired in the period August to October 2014 from the European Space Agency's Rosetta spacecraft when it was in close proximity to the nucleus of comet 67P/Churyumov-Gerasimenko. Aims: With our 3D gas and dust comae models this work attempts to test the hypothesis that cliff activity on comet 67P/Churyumov-Gerasimenko can solely account for the local gas density data observed by the Rosetta Orbiter Spectrometer for Ion and Neutral Analysis (ROSINA) and the dust brightnesses seen by the Optical, Spectroscopic, and Infrared Remote Imaging System (OSIRIS) in the considered time span. Methods: The model uses a previously developed shape model of the nucleus. From this, the water sublimation rates and gas temperatures at the surface are computed. The gas expansion is modelled with a 3D Direct Simulation Monte Carlo algorithm. A dust drag algorithm is then used to compute dust volume number densities in the coma, which are then converted to brightnesses using Mie theory and a line-of-sight integration. Furthermore we have studied the impact of topographic re-radiation on the models. Results: We show that gas activity from only cliff areas produces a fit to the ROSINA/COPS data that is as statistically good as a purely insolation-driven model. In contrast, pure cliff activity does not reproduce the dust brightness observed by OSIRIS and can thus be ruled out. On the other hand, gas activity from the Hapi region in addition to cliff activity produces a statistically better fit to the ROSINA/COPS data than purely insolation-driven outgassing and also fits the OSIRIS observations rather well. We found that topographic re-radiation does not contribute significantly to the sublimation behaviour of H2O but plays an important role in how the gas flux interacts with the irregular shape of the nucleus. Conclusions: We demonstrate that fits to the observations are non-unique. We can conclude however that gas and dust

  14. Correlation between Changes in Serum Level of CEA and CYFRA 21-1 and Objective Response of Chemotherapy

    Directory of Open Access Journals (Sweden)

    Xinlin MU

    2009-09-01

    Full Text Available Background and objective Serum levels of tumor markers are associated with tumor metabolism or apoptosis, changes of which after chemotherapy may reflect tumor response to treatment. The aim of this study was to assess the predictive role of changes in serum levels of carcinoembryonic antigen (CEA and cytokeratin 19 fragment (CYFRA 21-1 during chemotherapy in patients with advanced non-small cell lung cancer. Methods Changes in serum levels of CEA and CYFRA 21-1 were investigated retrospectively after one cycle of chemotherapy in 42 patients with advanced NSCLC. Correlations between the changes and radiological objective response were analyzed. Results After two cycles of chemotherapy, radiological objective response rate was 28.6%. At baseline, gender, age, clinical stage, serum levels of CEA and CYFRA 21-1 were not different between patients with objective response (OR and no response (NR. After one cycle of chemotherapy, compared to baseline level, declines in serum levels of CEA and CYFRA 21-1 were observed in patients with OR, but have no statistical significance. In contrast, reduction of CEA and CYFRA 21-1 over baseline after one cycle of chemotherapy showed statistically significant difference between OR and NR. When reduction percentages of CEA and CYFRA 21-1 were used to predict objective response of chemotherapy, the area under the ROC curve (AUC was 0.875 for CEA and 0.919 for CYFRA 21-1. According to the ROC curve, a 22% reduction of CEA yielded a sensitivity of 58.3% and a specificity of 97%, 51% reduction of CYFRA 21-1 with a sensitivity of 83.3% and a specificity of 93.3%. When above reduction percentages were used as cutoffs for prediction of radiological objective response, combination of the CEA and CYFRA 21-1 yielded a sensitivity of 91.7% and a specificity of 86.7%. Conclusion Reduction percentages of CEA and CYFRA 21-1 during chemotherapy could be used to evaluate chemotherapy efficacy in patients with advanced NSCLC. The

  15. The economics of fast breeder reactors

    International Nuclear Information System (INIS)

    Rapin, M.

    1990-01-01

    The overall status of the fast breeder reactor (FBR) system is periodically reviewed in France. In 1983, a report was prepared on the status and prospects of the FBR system at the request of the then Minister of Industry. Five years later, Electricite de France (EdF) and the French Atomic Energy Commission (CEA) jointly updated this report. The FBR reactor system economic considerations mentioned here are taken from the work performed in 1987-88 for this updating. The position in 1983 is reviewed to highlight concrete developments. Developments that have occurred since then are presented, along with the prospects that today enable us to define better the technical and economic potential of the FBR system. In conclusion, the effects of these findings on desirable directions are discussed, in particular with regard to European FBR cooperation. (author)

  16. Mechanical modelling of PCI with FRAGEMA and CEA finite element codes

    International Nuclear Information System (INIS)

    Joseph, J.; Bernard, Ph.; Atabek, R.; Chantant, M.

    1983-01-01

    In the framework of their common program, CEA and FRAGEMA have undertaken the mechanical modelization of PCI. In the first step two different codes, TITUS and VERDON, have been tested by FRAGEMA and CEA respectively. Whereas the two codes use a finite element method to describe the thermomechanical behaviour of a fuel element, input models are not the same for the two codes: to take into account the presence of cracks in UO 2 , an axisymmetric two dimensional mesh pattern and the Druecker-Prager criterion are used in VERDON and a 3D equivalent method in TITUS. Two rods have been studied with these two methods: PRISCA 04bis and PRISCA 104 which were ramped in SILOE. The results show that the stresses and strains are the same with the two codes. These methods are further applied to the complete series of the common ramp test rods program of FRAGEMA and CEA. (author)

  17. CEA: assessment of risk management 2011

    International Nuclear Information System (INIS)

    2012-06-01

    This report proposes an overview of CEA activities in the field of risk management in different areas: impact on the environment, installation safety, management of occupational risks (occupational health and safety), radiological protection of workers, transportation of hazardous materials, waste management, protection of sites, installations and heritage, management of emergency situations, management of law risks, controls and audits. It finally presents the risk management department

  18. Use of radioimmunodetection of carcinoembryonic antigen (CEA) and ferritin in diagnosis of lung cancer

    International Nuclear Information System (INIS)

    Zamyatin, S.S.; Zakharychev, V.D.

    1989-01-01

    To study the diagnostic value of radioimmunoassay (RIA) of carcinoembryonic antigen (CEA) and ferritin the level of this markers under lung cancer depending on the tumor localization and the process stage is determined. It is shown that determination of CEA and ferritin level in a number of patients with the peripheral lung cancer allows on the confirm the diagnosis. In case of the central cancer an increase of CEA level testifies to the tumor germination into the adjacent organs and lung tissue and allows one to determine the stage and operability of the disease. 10 refs.; 3 tabs

  19. Use of a combination of CEA and tumor budding to identify high-risk patients with stage II colon cancer.

    Science.gov (United States)

    Du, Changzheng; Xue, Weicheng; Dou, Fangyuan; Peng, Yifan; Yao, Yunfeng; Zhao, Jun; Gu, Jin

    2017-07-24

    High-risk patients with stage II colon cancer may benefit from adjuvant chemotherapy, but identifying this patient population can be difficult. We assessed the prognosis value for predicting tumor progression in patients with stage II colon cancer, of a panel of 2 biomarkers for colon cancer: tumor budding and preoperative carcinoembryonic antigen (CEA). Consecutive patients (N = 134) with stage II colon cancer who underwent curative surgery from 2000 to 2007 were included. Multivariate analysis was used to evaluate the association of CEA and tumor budding grade with 5-year disease-free survival (DFS). The prognostic accuracy of CEA, tumor budding grade and the combination of both (CEA-budding panel) was determined. The study found that both CEA and tumor budding grade were associated with 5-year DFS. The prognostic accuracy for disease progression was higher for the CEA-budding panel (82.1%) than either CEA (70.9%) or tumor budding grade (72.4%) alone. The findings indicate that the combination of CEA levels and tumor budding grade has greater prognostic value for identifying patients with stage II colon cancer who are at high-risk for disease progression, than either marker alone.

  20. Evaluation of detection methodology for carcinoembryonic antigen and application of CEA in diagnosis of gastric cancer

    International Nuclear Information System (INIS)

    Wang Enlan; Li Tao

    2005-01-01

    To compare the specificity and sensitivity of different methods in detection of CEA, and to investigate the application of CEA detection in diagnosis of gastric cancer, CEA in serum of 36 patients with gastric cancer and 20 negtive reference serum was detected by ELISA, TR- FIA, RIA and CLIA. The results showed that the specificity of these 4 methods was all 100% and the sensitivity of ELISA was the lowest (19.4%) while CLIA was the highest (44.4%). Therefore, the sensitivity of ELISA should be raised and CEA, besides used as an observation index for curative effects in a part of gastric cancer patients, can not be used in diagnosis of gastric cancer. (authors)

  1. Changes in the legal status of the Commissariat a l'energie atomique (Cea)

    International Nuclear Information System (INIS)

    Grammatico-Vidal, L.

    2009-01-01

    The Cea a public research institution was re-classified among the energy research establishments (11 december 2008). The Cea, as the result of exceptional circumstances and complex activities, is today entering into a new era and must confront many national and supranational challenges. It is preparing, in effect, for a future nuclear industry (safer, less polluting, non-proliferating and more economical) and is conducting research into other energy solutions within the framework of sustainable development and limited greenhouse gas effects (hydrogen technology, fusion, alternative energy technologies). It also has another goal, to make technological research available to industry, not only by developing micro and nano-technologies or even to contribute technology for the benefit of scientific knowledge of living creatures, matter, climate and the environment. The new classification of the Cea as a research establishment in the field of energy, a heading which includes three other entities (A.N.D.R.A., A.D.E.M.E. and I.F.P.), raises questions about its specialization and diversification. However, no substantive change was made to the drafting of the legislative provisions so it is possible to imagine that the Cea takes initiatives in other fields, at the instigation or with the approval of the government, a matter which is facilitated by its classification in the E.P.I.C. category (public establishment at industrial and commercial character). The Cea also represents France in international organisations in the nuclear sector, such as the OECD Nuclear energy agency (Nea), the International atomic energy agency (IAEA) and the European communities. It also participates in intergovernmental negotiations in the nuclear field and ensures any follow-up required with regard to any resulting agreements. today, the Cea plays a major role in the implementation of French nuclear policy with the aim of making available to countries wishing to develop nuclear energy, a framework

  2. New measurement system for on line in core high-energy neutron flux monitoring in materials testing reactor conditions

    International Nuclear Information System (INIS)

    Geslot, B.; Filliatre, P.; Barbot, L.; Jammes, C.; Breaud, S.; Oriol, L.; Villard, J.-F.; Vermeeren, L.; Lopez, A. Legrand

    2011-01-01

    Flux monitoring is of great interest for experimental studies in material testing reactors. Nowadays, only the thermal neutron flux can be monitored on line, e.g., using fission chambers or self-powered neutron detectors. In the framework of the Joint Instrumentation Laboratory between SCK-CEN and CEA, we have developed a fast neutron detector system (FNDS) capable of measuring on line the local high-energy neutron flux in fission reactor core and reflector locations. FNDS is based on fission chambers measurements in Campbelling mode. The system consists of two detectors, one detector being mainly sensitive to fast neutrons and the other one to thermal neutrons. On line data processing uses the CEA depletion code DARWIN in order to disentangle fast and thermal neutrons components, taking into account the isotopic evolution of the fissile deposit. The first results of FNDS experimental test in the BR2 reactor are presented in this paper. Several fission chambers have been irradiated up to a fluence of about 7 x 10 20 n/cm 2 . A good agreement (less than 10% discrepancy) was observed between FNDS fast flux estimation and reference flux measurement.

  3. New measurement system for on line in core high-energy neutron flux monitoring in materials testing reactor conditions

    Science.gov (United States)

    Geslot, B.; Vermeeren, L.; Filliatre, P.; Lopez, A. Legrand; Barbot, L.; Jammes, C.; Bréaud, S.; Oriol, L.; Villard, J.-F.

    2011-03-01

    Flux monitoring is of great interest for experimental studies in material testing reactors. Nowadays, only the thermal neutron flux can be monitored on line, e.g., using fission chambers or self-powered neutron detectors. In the framework of the Joint Instrumentation Laboratory between SCK-CEN and CEA, we have developed a fast neutron detector system (FNDS) capable of measuring on line the local high-energy neutron flux in fission reactor core and reflector locations. FNDS is based on fission chambers measurements in Campbelling mode. The system consists of two detectors, one detector being mainly sensitive to fast neutrons and the other one to thermal neutrons. On line data processing uses the CEA depletion code DARWIN in order to disentangle fast and thermal neutrons components, taking into account the isotopic evolution of the fissile deposit. The first results of FNDS experimental test in the BR2 reactor are presented in this paper. Several fission chambers have been irradiated up to a fluence of about 7 × 1020 n/cm2. A good agreement (less than 10% discrepancy) was observed between FNDS fast flux estimation and reference flux measurement.

  4. New measurement system for on line in core high-energy neutron flux monitoring in materials testing reactor conditions

    Energy Technology Data Exchange (ETDEWEB)

    Geslot, B.; Filliatre, P.; Barbot, L.; Jammes, C.; Breaud, S.; Oriol, L.; Villard, J.-F. [CEA, DEN, Cadarache, SPEx/LDCI, F-13108 Saint-Paul-lez-Durance (France); Vermeeren, L. [SCK-CEN, Boeretang 200, B-2400 Mol (Belgium); Lopez, A. Legrand [CEA, DEN, Saclay, SIREN/LECSI, F-91400 Saclay (France)

    2011-03-15

    Flux monitoring is of great interest for experimental studies in material testing reactors. Nowadays, only the thermal neutron flux can be monitored on line, e.g., using fission chambers or self-powered neutron detectors. In the framework of the Joint Instrumentation Laboratory between SCK-CEN and CEA, we have developed a fast neutron detector system (FNDS) capable of measuring on line the local high-energy neutron flux in fission reactor core and reflector locations. FNDS is based on fission chambers measurements in Campbelling mode. The system consists of two detectors, one detector being mainly sensitive to fast neutrons and the other one to thermal neutrons. On line data processing uses the CEA depletion code DARWIN in order to disentangle fast and thermal neutrons components, taking into account the isotopic evolution of the fissile deposit. The first results of FNDS experimental test in the BR2 reactor are presented in this paper. Several fission chambers have been irradiated up to a fluence of about 7 x 10{sup 20} n/cm{sup 2}. A good agreement (less than 10% discrepancy) was observed between FNDS fast flux estimation and reference flux measurement.

  5. Multiple myeloma presenting as CEA-producing rectal cancer.

    Science.gov (United States)

    Talamo, Giampaolo; Barochia, Amitkumar; Zangari, Maurizio; Loughran, Thomas P

    2010-03-31

    We report the case of a 57-year-old patient with multiple myeloma, characterized by extramedullary involvement of the rectum at presentation. Malignant plasma cells were found to produce carcinoembryonic antigen (CEA), a tumor antigen more commonly associated with rectal adenocarcinomas.

  6. Environmental monitoring of the Cea Valduc centre

    International Nuclear Information System (INIS)

    Guetat, Ph.; Jaskula, L.

    2010-01-01

    This paper describes the main features of the environmental control in the vicinity of the CEA Valduc centre, explains the site specific characteristics, the surveillance policy, and some historical elements about tritium atmospheric release. Some levels of activities are given, corresponding to an exposure level below 0.02% of natural irradiation. (author)

  7. Reprocessing ability of high density fuels for research and test reactors

    International Nuclear Information System (INIS)

    Gay, A.; Belieres, M.

    1997-01-01

    The development of a new high density fuel is becoming a key issue for Research Reactors operators. Such a new fuel should be a Low Enrichment Uranium (LEU) fuel with a high density, to improve present in core performances. It must be compatible with the reprocessing in an industrial plant to provide a steady back-end solution. Within the framework of a work group CEA/CERCA/COGEMA on new fuel development for Research Reactors, COGEMA has performed an evaluation of the reprocessing ability of some fuel dispersants selected as good candidates. The results will allow US to classify these fuel dispersants from a reprocessing ability point of view. (author)

  8. EPR by Areva. EPR the 1600+ MWe reactor

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    This brochure presents the GEN III+ EPR reactor designed by the Areva and Siemens consortium. The EPR reactor is a direct descendent of the well-proven N4 and KONVOI reactors, the most modern reactors in France and Germany. The EPR was designed by teams from KWU/Siemens and Framatome, EDF in France and the major German utilities, working in collaboration with both French and German safety authorities. The EPR integrates the results of decades of R and D programs, in particular those performed by the CEA (French Atomic Energy Commission) and the Karlsruhe Research Center in Germany. The EPR benefits from the experience of several thousand reactor-years of operation of pressurized water reactor technology. This experience has put 87 AREVA PWRs online throughout the world. Innovative Features: - An outer shell covering the reactor building, the spent fuel building and two of the four safeguard buildings provides protection against large commercial or military aircraft crash. - A heavy neutron reflector that surrounds the reactor core lowers uranium consumption. - An axial economizer inside the steam generator allows a high level of steam pressure and therefore high plant efficiency. - A core catcher allows passive collection and retention of the molten core should the reactor vessel fail in the highly unlikely event of a core melt. - A digital technology and a fully computerized control room with an operator friendly man-machine interface improve the reactor protection system.

  9. EPR by Areva. EPR the 1600+ MWe reactor

    International Nuclear Information System (INIS)

    2008-01-01

    This brochure presents the GEN III+ EPR reactor designed by the Areva and Siemens consortium. The EPR reactor is a direct descendent of the well-proven N4 and KONVOI reactors, the most modern reactors in France and Germany. The EPR was designed by teams from KWU/Siemens and Framatome, EDF in France and the major German utilities, working in collaboration with both French and German safety authorities. The EPR integrates the results of decades of R and D programs, in particular those performed by the CEA (French Atomic Energy Commission) and the Karlsruhe Research Center in Germany. The EPR benefits from the experience of several thousand reactor-years of operation of pressurized water reactor technology. This experience has put 87 AREVA PWRs online throughout the world. Innovative Features: - An outer shell covering the reactor building, the spent fuel building and two of the four safeguard buildings provides protection against large commercial or military aircraft crash. - A heavy neutron reflector that surrounds the reactor core lowers uranium consumption. - An axial economizer inside the steam generator allows a high level of steam pressure and therefore high plant efficiency. - A core catcher allows passive collection and retention of the molten core should the reactor vessel fail in the highly unlikely event of a core melt. - A digital technology and a fully computerized control room with an operator friendly man-machine interface improve the reactor protection system

  10. Diabody construct of ior-CEA1. Pre-clinical studies for therapeutic application

    International Nuclear Information System (INIS)

    Pimentel, G.; Ravelo, R.; Miranda, M.; Sanchez, I.; Perez, L.; Ayala, M.; Gavilondo, J.

    2007-01-01

    Full text: The classic radioimmunotherapy is based on transporting to the tumor, the necessary activity of a therapeutic isotope using a monoclonal antibody (MAb) against tumor associated antigen, which constitutes an ideal vehicle given its inherent specificity. In this sense, the immunoglobulin (Ig) has some severe practical limitations due to its unhappy pharmacokinetics, relatively high molecular weight (150 kDa) and slower clearance. Likewise the Ig molecule presents a poor diffusion through the tumor mass and a relative high immunogenicity. The solution to these problems has been offered by genetic engineering, methods where the multivalent recombinant fragments have become the paradigm of design of constructed molecules. They are able to retain the specificity of the parental antibody and affinity, with reduced immunogenicity and improved pharmacokinetics. The monoclonal antibody ior-CEA1 has been employed for the diagnosis of primary tumors, recurrences and metastatic disease, and has also been used extensively in the daily clinical practice as well. Inserted in this rebirth of the antibodies, this report explores the use of a new smaller molecular weight multivalent analogue of the parent ior-CEA1 antibody to be used for the diagnosis and therapy of CEA-expressing malignant tumors such as colorectal, lung, ovary among others. The dimeric scFv-ior- CEA1 construct was produced in the Centre for Genetic Engineering and Biotechnology and displayed to bind CEA epitope with a similar binding affinity to that of the murine IgG. Method: Labelling was achieved using Chloramine T, with a molar ration of Chloramine T:Tyrosine of 2.5. For the comparison of the immunoreactivity of labeled and unlabelled diabodies, was plotted the specific union vs the antibody concentration for both molecules and adjusted to a straight line. The immunoreactivity was also assayed using size-exclusion FPLC to evaluate their antigen-binding capacities after radiolabelling. Seventy

  11. The value of KRAS mutation testing with CEA for the diagnosis of pancreatic mucinous cysts

    Science.gov (United States)

    Kadayifci, Abdurrahman; Al-Haddad, Mohammad; Atar, Mustafa; Dewitt, John M.; Forcione, David G.; Sherman, Stuart; Casey, Brenna W.; Fernandez-del Castillo, Carlos; Schmidt, C. Max; Pitman, Martha B.; Brugge, William R.

    2016-01-01

    Background and aims: Pancreatic cyst fluid (PCF) CEA has been shown to be the most accurate preoperative test for detection of cystic mucinous neoplasms (CMNs). This study aimed to assess the added value of PCF KRAS mutational analysis to CEA for diagnosis of CMNs. Patients and methods: This is a retrospective study of prospectively collected endoscopic ultrasonography (EUS) fine-needle aspiration (FNA) data. KRAS mutation was determined by direct sequencing or equivalent methods. Cysts were classified histologically (surgical cohort) or by clinical (EUS or FNA) findings (clinical cohort). Performance characteristics of KRAS, CEA and their combination for detection of a cystic mucinous neoplasm (CMN) and malignancy were calculated. Results: The study cohort consisted of 943 patients: 147 in the surgical cohort and 796 in the clinical cohort. Overall, KRAS and CEA each had high specificity (100 % and 93.2 %), but low sensitivity (48.3 % and 56.3 %) for the diagnosis of a CMN. The positivity of KRAS or CEA increased the diagnostic accuracy (80.8 %) and AUC (0.84) significantly compared to KRAS (65.3 % and 0.74) or CEA (65.8 % and 0.74) alone, but only in the clinical cohort (P < 0.0001 for both). KRAS mutation was significantly more frequent in malignant CMNs compared to histologically confirmed non-malignant CMNs (73 % vs. 37 %, P = 0.001). The negative predictive value of KRAS mutation was 77.6 % in differentiating non-malignant cysts. Conclusions: The detection of a KRAS mutation in PCF is a highly specific test for mucinous cysts. It outperforms CEA for sensitivity in mucinous cyst diagnosis, but the data does not support its routine use. PMID:27092317

  12. Determination of the kinetic parameters of the CALIBAN metallic core reactor from stochastic neutron measurements

    Energy Technology Data Exchange (ETDEWEB)

    Casoli, P.; Authier, N.; Chapelle, A. [Commissariat a l' Energie Atomique et Aux Energies Alternatives, CEA, DAM, F-21120 Is sur Tille (France)

    2012-07-01

    Several experimental devices are operated by the Criticality and Neutron Science Research Dept. of the CEA Valduc Laboratory. One of these is the Caliban metallic core reactor. The purpose of this study is to develop and perform experiments allowing to determinate some of fundamental kinetic parameters of the reactor. The prompt neutron decay constant and particularly its value at criticality can be measured with reactor noise techniques such as Rossi-{alpha} and Feynman variance-to-mean methods. Subcritical, critical, and even supercritical experiments were performed. Fission chambers detectors were put nearby the core and measurements were analyzed with the Rossi-{alpha} technique. A new value of the prompt neutron decay constant at criticality was determined, which allows, using the Nelson number method, new evaluations of the effective delayed neutron fraction and the in core neutron lifetime. As an introduction of this paper, some motivations of this work are given in part 1. In part 2, principles of the noise measurements experiments performed at the CEA Valduc Laboratory are reminded. The Caliban reactor is described in part 3. Stochastic neutron measurements analysis techniques used in this study are then presented in part 4. Results of fission chamber experiments are summarized in part 5. Part 6 is devoted to the current work, improvement of the experimental device using He 3 neutron detectors and first results obtained with it. Finally, conclusions and perspectives are given in part 7. (authors)

  13. Diagnostic value of CEA and CYFRA 21-1 tumor markers in primary lung cancer.

    Science.gov (United States)

    Okamura, Kyoko; Takayama, Koichi; Izumi, Miiru; Harada, Taishi; Furuyama, Kazuto; Nakanishi, Yoichi

    2013-04-01

    Lung cancer is sometimes difficult to differentiate from benign lung diseases expressing nodular shadow in imaging study. We assessed the diagnostic value of two commonly used tumor markers in distinguishing primary lung cancer from benign lung disease. The serum levels of carcinoembryonic antigen (CEA) and cytokeratin 19 fragments (CYFRA 21-1) were retrospectively analyzed in 655 lung cancer patients and 237 patients with benign lung disease. The standard cut-off levels of 3.2 ng/mL CEA and 3.5 ng/mL CYFRA 21-1 and twice these respective levels (6.4 ng/mL and 7.0 ng/mL) were used. CEA and CYFRA 21-1 levels were elevated in 32% and 11% of benign lung disease patients, respectively. CEA sensitivity and specificity for lung cancer diagnosis was 69% and 68% respectively, while that for CYFRA 21-1 was 43% and 89%, respectively. Thus, the combined value for the specificity of the two tumor markers was greater than either alone. Patients were grouped depending on their hospital status, and prevalence rates were determined. The prevalence rate of lung cancer in admitted patients was 51%, the prevalence rate of lung cancer in outpatients was 12%, and the prevalence rate of lung cancer identified during health check-ups was 0.1%. Positive predictive values (PPVs) were calculated using Bayes' theorem, and varied with the serum tumor marker and prevalence rate: PPVs of CEA [prevalence rate] were 69.2% [51%], 22.7% [12%], and 0.22% [0.1%], while PPVs of CYFRA 21-1 were 80.3% [51%], 34.8% [12%], and 0.39% [0.1%]. However, PPVs for lung cancer diagnosis at a prevalence rate of 51% were 87.3% or higher when the patient exhibited positive CEA and CYFRA 21-1, or CEA or CYFRA 21-1 levels twice the standard cut-off. Our results indicate that CEA and CYFRA 21-1 are reliable serum tumor markers for the diagnosis of lung cancer in addition to CT scans when combined or used individually at twice the standard cut-off level in high prevalence rate groups. The prevalence rate should

  14. A new BETSI test bench at CEA/Saclay

    International Nuclear Information System (INIS)

    Nyckees, S.; Adroit, G.; Delferriere, O.; Duperrier, R.; Gauthier, Y.; Gobin, R.; Harrault, F.; Mateo, C.M.; Napoly, O.; Pottin, B.; Sauce, Y.; Senee, F.; Tuske, O.; Vacher, T.

    2012-01-01

    In the nineties, CEA has undertaken to develop the production of high intensity light ion beams from plasma generated by electron cyclotron resonance (ECR). Important results were obtained with the SILHI source in pulsed or continuous mode. Presently, CEA/Saclay is now involved in the construction of different injectors dedicated to large infrastructures like IFMIF or SPIRAL2. Other installations are also interested by high intensity ion sources like ESS or FAIR. To improve and test new sources, a new test bench named BETSI (Banc d'Etudes et de Tests des Sources d'Ions) has been operating for several years. Low energy beam line diagnostics consist of a Faraday cup, cameras and a species analyzer. The SILHI emittance scanner can also be installed on the beam line. On this test bench, different permanent magnet source configurations are tested. The paper is followed by the associated poster. (authors)

  15. Considerations concerning the reliability of reactor safety equipment

    International Nuclear Information System (INIS)

    Furet, J.; Guyot, Ch.

    1967-01-01

    A review is made of the circumstances which favor a good collection of maintenance data at the C.E.A. The large amount of data to be treated has made necessary the use of a computer for analyzing automatically the results collected. Here, only particular aspects of the reliability from the point of view of the electronics used for nuclear reactor control will be dealt with: sale and unsafe failures; probability of survival (in the case of reactor safety); availability. The general diagrams of the safety assemblies which have been drawn up for two types of reactor (power reactor and low power experimental reactor) are given. Results are presented of reliability analysis which could be applied to the use of functional modular elements, developed industrially in France. Improvement of this reliability appears to be fairly limited by an increase in the redundancy; on the other hand it is shown how it may be very markedly improved by the use of automatic tests with different frequencies for detecting unsafe failures rates of measurements for the sub-assemblies and for the logic sub-assemblies. Finally examples are given to show the incidence of the complexity and of the use of different technologies in reactor safety equipment on the reliability. (authors) [fr

  16. A structured approach to Exposure Based Waiving of human health endpoints under REACH developed in the OSIRIS project.

    Science.gov (United States)

    Marquart, Hans; Meijster, Tim; Van de Bovenkamp, Marja; Ter Burg, Wouter; Spaan, Suzanne; Van Engelen, Jacqueline

    2012-03-01

    Exposure Based Waiving (EBW) is one of the options in REACH when there is insufficient hazard data on a specific endpoint. Rules for adaptation of test requirements are specified and a general option for EBW is given via Appendix XI of REACH, allowing waiving of repeated dose toxicity studies, reproductive toxicity studies and carcinogenicity studies under a number of conditions if exposure is very low. A decision tree is described that was developed in the European project OSIRIS (Optimised Strategies for Risk Assessment of Industrial Chemicals through Integration of Non-Test and Test Information) to help decide in what cases EBW can be justified. The decision tree uses specific criteria as well as more general questions. For the latter, guidance on interpretation and resulting conclusions is provided. Criteria and guidance are partly based on an expert elicitation process. Among the specific criteria a number of proposed Thresholds of Toxicological Concern are used. The decision tree, expanded with specific parts on absorption, distribution, metabolism and excretion that are not described in this paper, is implemented in the OSIRIS webtool on integrated testing strategies. Copyright © 2011 Elsevier Inc. All rights reserved.

  17. Expert systems for analysis and management assistance of nuclear reactor electrical power supplies

    International Nuclear Information System (INIS)

    Evrard, J.M.; Souchet, Y.

    1988-01-01

    Electrical power supplies of nuclear plants are very complex systems. They are studied in many ways: failure consequences, probabilistic risk assessement, failure diagnosis, corrective actions in case of incident ... Knowledge base technology (expert systems) is very suited to solve these problems. A common structural representation can generate specific functional representations; thus we get coherency and easy evolution. This paper shows a two facet methodology: the plant description (both static and dynamic) and reasoning about it. Current applications are developed for pressurized water reactors and gas cooled reactors, using the SPIRAL expert system shell buil at CEA [fr

  18. High-temperature reactors: a recent past, a near future

    International Nuclear Information System (INIS)

    Ballot, B.

    2007-01-01

    While high-temperature reactors did experience major developments in the past, in Europe in particular, significant R and D efforts are required, if a major innovation deployment is to be made possible, of modular reactors having the capability of being coupled, in reliable, economic fashion, to an industrial process. The aim: the construction, before the next decade is out more swiftly than is feasible for other fourth-generation systems of an industrial prototype, coupled to such a process. The Areva Group takes up this approach, with its ANTARES project. For the purposes of characterizing the thermal properties of heterogeneous, multi-scale materials, as a function of temperature, experimental and numerical instruments have been developed at the Microstructure and Behavior Laboratory (Laboratoire microstructure et comportement), at CEA Le Ripault Center. They have been applied to the thermal characterization of the various layers in a high temperature reactor (HTR) fuel ball. (authors)

  19. THERMOS, district central heating nuclear reactors

    International Nuclear Information System (INIS)

    Patarin, L.

    1981-02-01

    In order to expand the penetration of uranium in the national energy balance sheet, the C.E.A. has been studying nuclear reactors for several years now, that are capable of providing heat at favourable economic conditions. In this paper the THERMOS model is introduced. After showing the attraction of direct town heating by nuclear energy, the author describes the THERMOS project, defines the potential market, notably in France, and applies the lay-out study to the Grenoble Nuclear Study Centre site with district communal heating in mind. The economic aspects of the scheme are briefly mentioned [fr

  20. Ior-CEA-1: Labelling, quality control and clinical evaluation

    International Nuclear Information System (INIS)

    Pimentel, G.J.

    1998-01-01

    Within the Co-ordinated Programme on Labelling, Quality Control and Evaluation of Monoclonal Antibodies, the IAEA has made a great effort to expand efficient labelling methods, mainly those with radioisotopes which have been used for radioimmunoscintigraphy. In this sense, more recently 99 Tc m has been mostly employed in the majority of the investigations due to its ideal physical characteristics. Efficient labelling of monoclonal antibodies depends on a number of factors including the method and way of the label incorporation into the protein. During the last years several direct labelling approaches have been developed, which led to attain simple and inexpensive methods for medical practice, as well as safe and stable techniques which bring accurate and good quality images. Accordingly, this paper describes the results obtained during last five years which come from the comparison among different labelling systems, passing through the quality control to test the labelled monoclonal stability and the protein bioreactivity, to continue in the clinical evaluation of ior-CEA-1, as well as the evaluation of other antibodies. Up to now we have evaluated more than 70 patients with the anti-CEA monoclonal antibody (ior-CEA-1), examined in different clinical assays such as: pilot, phase I-II and extensive phase III-IV trials, whose results are encouraging. It confirms that the employed labelling approach was safe and adequate

Some links on this page may take you to non-federal websites. Their policies may differ from this site.