WorldWideScience

Sample records for french phenix fast

  1. The irradiation test program for transmutation in the French Phenix fast reactor

    International Nuclear Information System (INIS)

    Guidez, J.; Chaucheprat, P.; Fontaine, B.; Brunon, E.

    2004-01-01

    Put on commercial operation in July 1974, the French fast reactor Phenix reached a 100 000 hours operation time in september 2003. When the French law relative to long lived radioactive waste management was promulgated on December 1991, priority was given to Phenix to be run as a research reactor and to carry on a wide irradiation program dedicated to study transmutation of minor actinides and long-lived fission products. After a major renovation program required to extend the reactor lifetime, Phenix power buildup took place in 2003. Experimental irradiations have been loaded in the core, involving components for heterogeneous and homogeneous transmutation modes, americium targets, technetium 99 metal pins and isolated isotopes for integral cross-sections measurements. Associated post- irradiated examination programs are already underway or planned. With new experiments to be loaded in the core in 2006 the Phenix reactor remains to be a powerful tool providing an important experimental data on fast reactors and on transmutation of minor actinides and long-lived fission products, as well as it will contribute to gain further experience in the framework of the GENERATION IV International Forum. (authors)

  2. Development of French programme on fast reactors, from March 1976 to March 1977

    International Nuclear Information System (INIS)

    Vautrey, L.

    1977-01-01

    The following milestones of the French LMFBR programme are reported: RAPSODIE (irradiation experiments in order to study the behaviour of the different fuel components of a sodium cooled fast reactor); PHENIX (the burn-up of the first core has reached the nominal value of 50,000MWD/T); SUPER-PHENIX (status of construction)

  3. PHENIX Fast TOF

    Energy Technology Data Exchange (ETDEWEB)

    Soha, Aria [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Chiu, Mickey [Brookhaven National Lab. (BNL), Upton, NY (United States); Mannel, Eric [Brookhaven National Lab. (BNL), Upton, NY (United States); Stoll, Sean [Brookhaven National Lab. (BNL), Upton, NY (United States); Lynch, Don [Brookhaven National Lab. (BNL), Upton, NY (United States); Boose, Steve [Brookhaven National Lab. (BNL), Upton, NY (United States); Northacker, Dave [Brookhaven National Lab. (BNL), Upton, NY (United States); Alfred, Marcus [Howard Univ., Washington, DC (United States); Lindesay, James [Howard Univ., Washington, DC (United States); Chujo, Tatsuya [Univ. of Tsukuba (Japan); Inaba, Motoi [Univ. of Tsukuba (Japan); Nonaka, Toshihiro [Univ. of Tsukuba (Japan); Sato, Wataru [Univ. of Tsukuba (Japan); Sakatani, Ikumi [Univ. of Tsukuba (Japan); Hirano, Masahiro [Univ. of Tsukuba (Japan); Choi, Ihnjea [Univ. of Illinois, Urbana-Champaign, IL (United States)

    2014-01-15

    This is a technical scope of work (TSW) between the Fermi National Accelerator Laboratory (Fermilab) and the experimenters of PHENIX Fast TOF group who have committed to participate in beam tests to be carried out during the FY2014 Fermilab Test Beam Facility program. The goals for this test beam experiment are to verify the timing performance of the two types of time-of-flight detector prototypes.

  4. Status of fast reactors and ADS programmes in France in 2001

    International Nuclear Information System (INIS)

    Astegiano, J.C.

    2002-01-01

    Status of French fast reactor and ADS program in France covers the following topics: data on power generation from NPPs; status of fast reactors, namely Rapsodie, Phenix and Super Phenix; research and development programs concerned with fast gas cooled and sodium cooled reactors

  5. Pre-analysis of Phenix End-of-Life Thermal-hydraulic tests with the MARS-LMR Code

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Kwon, Young Min; Chang, Won Pyo; Suk, Su Dong; Lee, Yong Bum

    2009-01-01

    A prototype SFR, PHENIX has been operated by the French Commissariat a l'energie atomique (CEA) and the Electricite de France (EdF) since 1973. Through the successful operation for 35 years, PHENIX has achieved its original objective to demonstrate a fast breeder reactor technology and also played an important role as an irradiation facility for innovative fuels and materials. Since its first operation, PHENIX has accumulated about 4,300 equivalent full power days (EFPDs) of operational experience and it reached its final shutdown in 2009. Before the decommissioning of PHENIX, the CEA started a PHENIX end-of-life (EOL) test program and opened it for international collaboration to share the valuable information from the test. The KAERI joined this program to utilize the unique opportunity to validate its SFR system analysis code, MARS-LMR which will be a basic tool in future SFR development

  6. The PHENIX experimental irradiation program

    International Nuclear Information System (INIS)

    Michel, P.; Courcon, P.; Coulon, P.

    1985-03-01

    The PHENIX experimental irradiation program represents a substancial volume of work. For example, more than forty experiments were in the core during the 33rd PHENIX irradiation cycle at the end of 1984. This program ensures the implementation, optimization and qualification of new solutions for the future developpment of French LMFBRs in three significant areas: fissile, fertile and absorber elements

  7. 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)

  8. Containment Safety Of Super Phenix : Essai Mars

    Science.gov (United States)

    Falgayrettes, M. F.; Fiche, C.; Hamon, P.

    1985-02-01

    The protection of people and property must be assured by every situation around an industrial power plant. That is why the FRENCH Commissariat a l'Energie Atomique has defined the size of the confinement of Super Phenix to withstand the worst highly hypothetical accident. The study of the strength of the confinement has been carried out by two complementary means : - Calculation (Display poster # 491 188), - Experiment : reactor mock-up. The latter is presented in the film. The solution which have been adopted for the problems encountered are emphasied ; the work with high speed camera is presented. The film is illustrated with some fast movie sequences.

  9. Acoustic detection of a cavitation noise in the French breeder reactor Phenix

    International Nuclear Information System (INIS)

    Brunet, M.; Desprets, A.

    1981-06-01

    The French Phenix reactor is provided with an in-core multi-sensor acoustic surveillance system. But its efficiency with regard to early boiling detection is still to be proven. For lack of boiling events within the core, a cavitating dummy steel subassembly has been loaded into the reactor, as a simulation of boiling signal. Cavitation is controlled through a slow rise of the primary flow in various core conditions: isothermal situation and during a rise of power. Assuming that the signal to noise ratio is of the same order of magnitude for cavitation signals as for boiling ones, the response of several signal processing techniques is evaluated. Pulse connecting seems to be the most efficient conventional method while pattern recognition appears as a promising alternative solution

  10. Review of In-Service Inspection and Repair Technique Developments for French Liquid Metal Fast Reactors

    International Nuclear Information System (INIS)

    Baque, F.

    2005-01-01

    In-service monitoring of nuclear plants is indispensable for both the Operator and the Regulator. The notion of in-service monitoring ranges from the continuous monitoring of the reactor in operation to the thorough in-service reactor inspection during programmed shutdowns. However, the highly specific environment found in French liquid metal fast reactor plants - Phenix and Superphenix - makes monitoring and inspection complicated because of the use of a sodium coolant that is hot, opaque, and difficult to drain.The Commissariat a l'Energie Atomique, in collaboration with its traditional French partners, Electricite de France utilities and FRAMATOME/Novatome Engineering, decided to conduct a 6-yr research and development program (1994-2000) to explore this problem vis-a-vis Superphenix, as well as the possibilities of intervening within the reactor block or on components in a sodium environment. Furthermore, the safety reevaluation of Phenix, conducted between 1994 and 2003, represented an excellent 'test bench' during which the limits of inspection processes - applied to an integrated reactor concept - were surpassed using techniques such as fuel subassembly head scanning, ultrasonic examination of the core support, and visual inspection of the cover-gas plenum following a partial sodium draining. Repair techniques were investigated for cleaning of sodium wet structure surfaces, cutting of damaged parts, and welding in sodium aerosol atmosphere. Both conventional and laser processes were tested

  11. One day, Phenix..

    International Nuclear Information System (INIS)

    2010-01-01

    This book is mainly a collection of pictures taken at the Phenix fast breeder reactor site of Marcoule (France). A brief introduction summarizes the life of the reactor, from the decision of its construction taken in 1968, to its shutdown in 2009. During its first 17 years of existence, the reactor has played the role of demonstrator for the sodium-cooled FBR technology. The experience feedback is enormous. Less than 10 years after its start-up Phenix has demonstrated its breeding capacity at a quasi-industrial scale. Phenix has also demonstrated the feasibility of the minor actinides transmutation. From 1994 to 1997 and from 1998 to 2003 the reactor has been the object of deep renovations allowing its full power operation and the carrying out of irradiation experiments. On March 6, 2009 the reactor was disconnected from the grid. (J.S.)

  12. Advanced In-Service Inspection Approaches Applied to the Phenix Fast Breeder Reactor

    International Nuclear Information System (INIS)

    Guidez, J.; Martin, L.; Dupraz, R.

    2006-01-01

    The safety upgrading of the Phenix plant undertaken between 1994 and 1997 involved a vast inspection programme of the reactor, the external storage drum and the secondary sodium circuits in order to meet the requirements of the defence-in-depth safety approach. The three lines of defence were analysed for every safety related component: demonstration of the quality of design and construction, appropriate in-service inspection and controlling the consequences of an accident. The in-service reactor block inspection programme consisted in controlling the core support structures and the high-temperature elements. Despite the fact that limited consideration had been given to inspection constraints during the design stage of the reactor in the 1960's, as compared to more recent reactor projects such as the European Fast Reactor (EFR), all the core support line elements were able to be inspected. The three following main operations are described: Ultrasonic inspection of the upper hangers of the main vessel, using small transducers able to withstand temperatures of 130 deg. C, Inspection of the conical shell supporting the core dia-grid. A specific ultrasonic method and a special implementation technique were used to control the under sodium structure welds, located up to several meters away from the scan surface. Remote inspection of the hot pool structures, particularly the core cover plug after partial sodium drainage of the reactor vessel. Other inspections are also summarized: control of secondary sodium circuit piping, intermediate heat exchangers, primary sodium pumps, steam generator units and external storage drum. The pool type reactor concept, developed in France since the 1960's, presents several favourable safety and operational features. The feedback from the Phenix plant also shows real potential for in-service inspection. The design of future generation IV sodium fast reactors will benefit from the experience acquired from the Phenix plant. (authors)

  13. Multi-dimensional approach of MARS-LMR for the analysis of Phenix End-of-Life natural circulation test

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Chang, Won Pyo; Lee, Kwi Lim

    2012-01-01

    Phenix is one of the important prototype sodium-cooled fast reactors (SFR) in nuclear reactor development history. It had been operated successfully for 35 years by the French Commissariat a l'energie atomique (CEA) and the Electricite de France (EdF) achieving its original objectives of demonstrating a fast breeder reactor technology and of playing the role of irradiation facility for innovative fuels and materials. After its final shutdown in 2009, CEA launched the Phenix End-of-life (EOL) test program. It provided a unique opportunity to generate reliable test data which is inevitable in the validation and verification of a SFR system analysis code. KAERI joined this international collaboration program of IAEA CRP and has performed the pretest analysis and post-test analysis utilizing the one-dimensional modeling of the MARS-LMR code, which had been developed by KAERI for the transient analysis of SFR systems. Through the previous studies, it has been identified that there are some limitations in the modeling of complicated thermal-hydraulic behaviors in the large pool volumes with the one-dimensional modeling. Recently, KAERI performed the analysis of Phenix EOL natural circulation test with multi-dimensional pool modeling, which is detailed below

  14. Multi-dimensional approach of MARS-LMR for the analysis of Phenix End-of-Life natural circulation test

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Hae Yong; Ha, Kwi Seok; Chang, Won Pyo; Lee, Kwi Lim [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Phenix is one of the important prototype sodium-cooled fast reactors (SFR) in nuclear reactor development history. It had been operated successfully for 35 years by the French Commissariat a l'energie atomique (CEA) and the Electricite de France (EdF) achieving its original objectives of demonstrating a fast breeder reactor technology and of playing the role of irradiation facility for innovative fuels and materials. After its final shutdown in 2009, CEA launched the Phenix End-of-life (EOL) test program. It provided a unique opportunity to generate reliable test data which is inevitable in the validation and verification of a SFR system analysis code. KAERI joined this international collaboration program of IAEA CRP and has performed the pretest analysis and post-test analysis utilizing the one-dimensional modeling of the MARS-LMR code, which had been developed by KAERI for the transient analysis of SFR systems. Through the previous studies, it has been identified that there are some limitations in the modeling of complicated thermal-hydraulic behaviors in the large pool volumes with the one-dimensional modeling. Recently, KAERI performed the analysis of Phenix EOL natural circulation test with multi-dimensional pool modeling, which is detailed below

  15. Seismic re-evaluation of French nuclear power plants

    International Nuclear Information System (INIS)

    Andrieu, R.

    1995-01-01

    After a presentation of the seismic inputs which have been taken into account in the design of the French Nuclear Power Plants, the re-assessed values of these inputs are shown. Some considerations about the specificity of the French PWR program with regard to the standardisation of plants are given together with the present objectives of seismic re-evaluations. Finally the main results of the seismic re-analysis being performed for the Phenix Fast Reactor are considered. (author)

  16. Advances in neutronics calculation of fast neutron reactors - Demonstration on Super-Phenix reactor

    International Nuclear Information System (INIS)

    Czernecki, Sebastien

    1998-01-01

    The fast reactor european neutronics calculations system, ERANOS, has integrated recent improvements both in nuclear data, with the use of the adjusted nuclear library ERALIB 1 from the JEF2.2 library, and calculation methods, with the use of the new european cell code, ECCO, and the deterministic code, TGV/VARIANT. This code performs full 3-D reactor calculation in the transport theory with variational method. The aim of this work is to create and validate a new calculational scheme for fast spectrum systems offering good compromise between accuracy and running time. The new scheme is based on these improvements plus a special procedure accounting for control rod heterogeneity, which uses a reactivity equivalence homogenization. The new scheme has been validated by means of experiment/calculation comparisons, using the extensive start-up program measurements performed in Super-Phenix reactor. The validation uses also recent measurements performed in the Phenix reactor. The results are very satisfactory and show a significant improvement for almost all core parameters, especially for critical mass, control rod worth and radial subassembly power distribution. A detailed analysis of the discrepancies between the old scheme and the new one for this parameter allows to understand the separate effects of methods and nuclear data on the radial power distribution shape. (author) [fr

  17. Inter-vessels in-service inspection of Super-Phenix

    International Nuclear Information System (INIS)

    Asty, M.; Saglio, R.; Viard, J.; Lerat, B.

    1984-01-01

    The vessels design of fast breeder reactor Super-Phenix enables inspection during operating time. A self-moving machine -MIR- has been built up especially for that purpose. It is able to carry out visual and ultrasonorous inspection. MIR structure is that of a tetrahedron, all tops of which are fitted with two wheels, as for traction and direction. The wheels are leaning on booth the two vessels. Thanks to a computer-assisted control system, MIR is able to move along in every part of the inter-vessels space. Studies have been carried on at the French Commissariat a l'Energie Atomique, by two Sections of the advanced technologies Service. After outlining MIR working conditions, its main characteristics are described [fr

  18. Steam generator development in France for the Super Phenix project; Generateurs de vapeur developpes en France pour Super Phenix

    Energy Technology Data Exchange (ETDEWEB)

    Robin, M G

    1975-07-01

    'Steam Generator Development for Super Phenix Project'. The development program of steam generators studied by Fives-Cail Babcock and Stein Industrie Companies, jointly with CEA end EDF, for the Super Phenix 1200 MWe Fast Breeder Power Plant, is presented. The main characteristics of both sodium heated steam generators are emphasized and experimental studies related to their key features are reported. (author)

  19. Impressive Super Phenix

    International Nuclear Information System (INIS)

    Olds, F.C.

    1979-01-01

    The 1200-MWe fast breeder reactor, Super Phenix at Creys-Malville, is scheduled for commercial operation in 1983. This is the world's first near-commercial-sized fast breeder. As a near-commercial-sized unit, it represents essentially the technology and hardware of the first fully commercial follow-on units. In its size, its components, its design, the technology it represents, and its project schedule, it is impressive. As of May 1979, the Super Phenix nuclear steam boiler in the Creys-Malville plant bore an estimated cost of $700 million, without fuel. The total cost of the Creys-Malville plant now is estimated at about $1.4 billion. This is about twice the cost of a comparable standardized PWR being built in France today. However, it should be borne in mind that Creys-Malville carries the high cost of a first-of-the-line prototype, and that France's PWRs are standardized, second-generation units. Electricity from Creys-Malville is estimated to cost a little more than electricity would cost from a coal-fired plant complete with flue gas scrubbing

  20. Status of French breeder development and German-French cooperation

    International Nuclear Information System (INIS)

    Vendryes, G.

    1978-01-01

    The development of fast breeder reactors in France is at present characterized by the successful operation of the 250 MW reactor, Phenix, and the speedy progress made in construction of the 1200 MW Superphenix plant. The technical concept of Superphenix is a logical extension of the Phenix concept, i.e., the pool type sodium cooled breeder reactor. While the only change in the primary system has been an increase in capacity, the main modification over Phenix is the change from small modular steam generators to four large units. The development of the work to date does not cast any doubt upon the envisaged date of first criticality in the second half of 1982. The basis of German-French cooperation is a joint declaration by the then Ministers for Research of the two countries on February 13, 1976 in which the Ministers had expressed themselves in favor of close cooperation between both countries in the development of safe, reliable and economic fast breeder reactors. On this basis, the two governments, the research centers and the industrial partners in the two countries, including the previous partners in Belgium, the Netherlands and Italy, agreed on the general principles of this cooperation. Meanwhile, the cooperation formalized in 1977 has been activated. Both in research and development and among planning and building industries the exchange of know-how and cooperation is in full swing. The joint company, SERENA, is the pool for the know-how introduced by the partners and the sole representative of the partners in the scheme. (orig.) 891 UA [de

  1. International benchmark on the natural convection test in Phenix reactor

    International Nuclear Information System (INIS)

    Tenchine, D.; Pialla, D.; Fanning, T.H.; Thomas, J.W.; Chellapandi, P.; Shvetsov, Y.; Maas, L.; Jeong, H.-Y.; Mikityuk, K.; Chenu, A.; Mochizuki, H.; Monti, S.

    2013-01-01

    Highlights: ► Phenix main characteristics, instrumentation and natural convection test are described. ► “Blind” calculations and post-test calculations from all the participants to the benchmark are compared to reactor data. ► Lessons learned from the natural convection test and the associated calculations are discussed. -- Abstract: The French Phenix sodium cooled fast reactor (SFR) started operation in 1973 and was stopped in 2009. Before the reactor was definitively shutdown, several final tests were planned and performed, including a natural convection test in the primary circuit. During this natural convection test, the heat rejection provided by the steam generators was disabled, followed several minutes later by reactor scram and coast-down of the primary pumps. The International Atomic Energy Agency (IAEA) launched a Coordinated Research Project (CRP) named “control rod withdrawal and sodium natural circulation tests performed during the Phenix end-of-life experiments”. The overall purpose of the CRP was to improve the Member States’ analytical capabilities in the field of SFR safety. An international benchmark on the natural convection test was organized with “blind” calculations in a first step, then “post-test” calculations and sensitivity studies compared with reactor measurements. Eight organizations from seven Member States took part in the benchmark: ANL (USA), CEA (France), IGCAR (India), IPPE (Russian Federation), IRSN (France), KAERI (Korea), PSI (Switzerland) and University of Fukui (Japan). Each organization performed computations and contributed to the analysis and global recommendations. This paper summarizes the findings of the CRP benchmark exercise associated with the Phenix natural convection test, including blind calculations, post-test calculations and comparisons with measured data. General comments and recommendations are pointed out to improve future simulations of natural convection in SFRs

  2. Breeding characteristics analysis of a commercial fast reactor cooled with sodium liquid

    International Nuclear Information System (INIS)

    Kosaka, N.; Shigehiro, A.

    1982-01-01

    The fast reactor breeding characteristics and its safety is analysed. As reference, for a preliminar analysis, the specifications of Super-Phenix, reactor french of 1200 MWe, are used, varying some parameters after aiming to verify its effects on duplication time. (E.G.) [pt

  3. Improving PHENIX search with Solr, Nutch and Drupal

    International Nuclear Information System (INIS)

    Morrison, Dave; Sourikova, Irina

    2012-01-01

    During its 20 years of R and D, construction and operation the PHENIX experiment at the Relativistic Heavy Ion Collider (RHIC) has accumulated large amounts of proprietary collaboration data that is hosted on many servers around the world and is not open for commercial search engines for indexing and searching. The legacy search infrastructure did not scale well with the fast growing PHENIX document base and produced results inadequate in both precision and recall. After considering the possible alternatives that would provide an aggregated, fast, full text search of a variety of data sources and file formats we decided to use Nutch [1] as a web crawler and Solr [2] as a search engine. To present XML-based Solr search results in a user-friendly format we use Drupal [3] as a web interface to Solr. We describe the experience of building a federated search for a heterogeneous collection of 10 million PHENIX documents with Nutch, Solr and Drupal.

  4. Improving PHENIX search with Solr, Nutch and Drupal.

    Science.gov (United States)

    Morrison, Dave; Sourikova, Irina

    2012-12-01

    During its 20 years of R&D, construction and operation the PHENIX experiment at the Relativistic Heavy Ion Collider (RHIC) has accumulated large amounts of proprietary collaboration data that is hosted on many servers around the world and is not open for commercial search engines for indexing and searching. The legacy search infrastructure did not scale well with the fast growing PHENIX document base and produced results inadequate in both precision and recall. After considering the possible alternatives that would provide an aggregated, fast, full text search of a variety of data sources and file formats we decided to use Nutch [1] as a web crawler and Solr [2] as a search engine. To present XML-based Solr search results in a user-friendly format we use Drupal [3] as a web interface to Solr. We describe the experience of building a federated search for a heterogeneous collection of 10 million PHENIX documents with Nutch, Solr and Drupal.

  5. Leak detection in Phenix and Super Phenix steam generators

    Energy Technology Data Exchange (ETDEWEB)

    Cambillard, E [Centre d' Etudes Nucleaires de Saclay, Gif-sur-Yvette (France)

    1978-10-01

    Water leak detection Phenix and Super Phenix steam generators is based on measurement of the hydrogen produced by the reaction of sodium with water. The hydrogen evolves in the sodium in which the steam generator tubes are completely immersed. Depending on service conditions, however (sodium temperature and flow velocity), the hydrogen may appear in the argon existing above the free levels. This is why, although the Phenix steam generators do not feature free levels, measurement systems were added to measure the hydrogen concentration in the argon in the expansion tanks. Super Phenix steam generators are fitted at their outlet with systems for measuring hydrogen in the sodium, and above their free level with a system for measuring hydrogen in the argon. The measurement systems have nickel tube probes connected to circuits kept under vacuum by an ion pump. The hydrogen partial pressure is measured by a mass spectrometer. Super Phenix measurement systems differ from Phenix systems essentially in the temperature regulation of the sodium reaching the nickel tube probes, and in the centralization of the supply and measurement systems of the ion pumps and mass spectrometers. This paper deals with description, calibration and operating conditions of the hydrogen detection systems in sodium and argon in Phenix and Super Phenix steam generators. (author)

  6. The future of PHENIX: upgrading to sPHENIX and beyond

    Directory of Open Access Journals (Sweden)

    Mannel E.J.

    2015-01-01

    Full Text Available sPHENIX is a major upgrade to the PHENIX detector enabling high-rate, large acceptance measurements of upsilons, direct photons and fully reconstructed jets in p-p, p-A and A-A collisions at the Relativistic Heavy Ion Collider (RHIC. These detailed measurements will probe the Quark Gluon Plasma near its transition temperature, in a region of strongest coupling. The sPHENIX detector consists of hadronic and electromagnetic calorimetry, and charged particle tracking in conjunction with the recently acquired 1.5 tesla BaBar super-conducting solenoid. The sPHENIX acceptance of 2π in azimuth and |η| < 1.1 in pseudo-rapidity provides a factor of six improvement over the present PHENIX central spectrometer. Beyond being an excellent RHIC detector, sPHENIX provides an outstanding foundation for a detector focused on the physics of a possible future electron-ion collider at RHIC (eRHIC. In this talk we will discuss the physics potential of the sPHENIX detector, the design and technology choices for the sPHENIX calorimeters, and the conceptual design of a day-one detector for eRHIC.

  7. Super Phenix 1 fuel cycle, technical and economical outlooks

    International Nuclear Information System (INIS)

    Mougniot, J.C.; Baumier, J.; Duchatelle, L.

    1982-01-01

    An analysis of the costs of the various parts of the Super Phenix 1 fuel cycle is presented. The basis for calculating the mean levelized present unit cost used in French economic analyses is described. A description of the fuel cycle which follows includes the physical characteristics and management of the fuel and the costs of fuel services and raw materials. The results of calculations about Super Phenix mean levelized present fuel cycle unit cost are indicated and a comparison with two, four and six 1500 MWe units and PWR units is made. Finally conclusions are drawn about the economic possibility of FBR deployment. (U.K.)

  8. Steam generator development in France for the Super Phenix project

    International Nuclear Information System (INIS)

    Robin, M.G.

    1975-01-01

    'Steam Generator Development for Super Phenix Project'. The development program of steam generators studied by Fives-Cail Babcock and Stein Industrie Companies, jointly with CEA end EDF, for the Super Phenix 1200 MWe Fast Breeder Power Plant, is presented. The main characteristics of both sodium heated steam generators are emphasized and experimental studies related to their key features are reported. (author)

  9. PHENIX REPORTS

    International Nuclear Information System (INIS)

    Thompson, Timothy C.

    1998-01-01

    This report contains individual progress reports for the months of December 1997 through May 1998 on the Phenix program at Hytec. Topics include the Phenix muon detector chamber flow analysis; the Phenix Muon detector deformation and motion/tolerance study of Stations 1, 2, and 3; finite element mount/electron shield structural analysis; South Station 3 muon detector deformation analysis; and Station 1 muon detector panel assembly and fabrication sequences

  10. PHENIX REPORTS

    Energy Technology Data Exchange (ETDEWEB)

    TIMOTHY C. THOMPSON - HYTEC, INC.

    1998-12-10

    This report contains individual progress reports for the months of December 1997 through May 1998 on the Phenix program at Hytec. Topics include the Phenix muon detector chamber flow analysis; the Phenix Muon detector deformation and motion/tolerance study of Stations 1, 2, and 3; finite element mount/electron shield structural analysis; South Station 3 muon detector deformation analysis; and Station 1 muon detector panel assembly and fabrication sequences.

  11. PHENIX for Beginners

    Science.gov (United States)

    Zajc, W. A.; Fachini, P.

    2002-10-01

    An introduction to the PHENIX detector and to the PHENIX physics program is presented. The PHENIX physics results presented here are those from the the first RHIC (Relativistic Heavy Ion Collider) run with Au+Au collisions at RADICAL:[[RADICAND:[SNN

  12. Knowledge Preservation and Data Collection on Fast Reactors in France

    International Nuclear Information System (INIS)

    Vasile, A.

    2013-01-01

    Documentary packages: • MADONA - the French LMFR R&D Documentary collection; - A trilateral CEA, EDF & AREVA collection, 64 synthesis reports with 5300 relevant documents, on line. • RAPSODIE documentary collection - 18000 documents including 8000 drawings gathering available technical information on RAPSODIE; • PHENIX documentary fund - 140 000 documents. Design, specification, drawings, procedures, technical reports gathering available technical information on the PHENIX plant since 1968; • PHENIX lifetime extension project data base - 2000 reports. General methodology and feedback experience; • SUPERPHENIX Plant Archives - Several thousand of documents covering plant design, operation and decommissioning, since 1977; • SPX Safety report - 150 000 pages; - Plant characteristics & Technical options; - General safety analysis; - Manufacturing and operational rules (normal, incidental and anticipated operating conditions); • EFR 98 design documentation - around 5700 documents produced during the EFR studies; • EFR Synthesis reports - 48 synthesis reports; • ACCORE - 20 200 CEA technical documents on the period 1988-2001, with keyword research system; • The Fast Neutron Reactor System Knowledge Book - approx. 1400 licensing documents; • Sodium Technology data base - around 5500 technical documents on sodium circuits, sodium leak and fires, instrumentation, ISI&R, sodium water reaction in SG…; • CIR - The Reprocessing Information Centre data base gathered 25 000 reports, on reprocessing and analytical chemistry; among them around 600 reports concern Fast Reactor fuel reprocessing technology; • Database - Preservation of data relative to fast critical mock-ups: MASURCA (F), SNEAK(D), ZPPR (US), ZEBRA(UK), RRR/SEG(D). • ARCOPAC - Electronic data base on SUPERPHENIX physical measurements; • BREF Fuel Data Base - SFR fuels, behavior of structural materials; • Fatigue experimental data base for 316LN; • PHENIX expert Data base - Built

  13. PHENIX for beginners

    International Nuclear Information System (INIS)

    Zajc, W.A.; Fachini, P.

    2002-01-01

    An introduction to the PHENIX detector and to the PHENIX physics program is presented. The PHENIX physics results presented here are those from the the first RHIC (Relativistic Heavy Ion Collider) run with Au+Au collisions at √(S NN ) = 130 GeV. A brief overview of the PHENIX detector is provided. The systematic variation with centrality of charged particle multiplicity, transverse energy, identified particle spectra and yield ratios, production of charged hadrons and π0's at high transverse momenta are reported, together with first results on charm production at RHIC

  14. Smart Trigger Pre-Processor Custom Electronics for the PHENIX Experiment

    International Nuclear Information System (INIS)

    Nagle, James L.

    2003-01-01

    OAK-B135 The document provides a final technical report on activities and accomplishments of the experimental relativistic heavy ion physics group at the University of Colorado at Boulder as supported by the Outstanding Junior Investigator Program, Division of Nuclear Physics at the Department of Energy. All of the goals of the grant proposal were achieved during this last year of the Outstanding Junior Investigator funding period. The development of a Smart Trigger Pre-Processor module for fast trigger primitive calculations in the PHENIX experiment has been completed. We finalized the board design, constructed and tested two prototype modules, and with additional funding from the PHENIX project, we fabricated a full set of 15 modules for the Muon Tracking system. During Run-4 at RHIC:, we have begun the process of integrating these modules into the PHENIX data acquisition system, Additionally, we put a large Effort into developing new trigger and fast-track analysis methods for J j J data filtering and reconstruction. These algorithms make use of the trigger primitivE∼s generated via the new electronics

  15. Fast reactors. Thermal calculations of annulus application to Phenix

    International Nuclear Information System (INIS)

    Kung, J.P.; Gama, J.M.

    1975-01-01

    The gas convection phenomena involved in the annuli of the penetrations of the heat exchanger of the Phenix reactor are analyzed and the calculations performed using the BINIX program developed by GAAA to study the same phenomena are presented. The theory/experience comparison led to a better understanding of thermo-siphon phenomena [fr

  16. Benchmark Analyses on the Natural Circulation Test Performed During the PHENIX End-of-Life Experiments. Final Report of a Co-ordinated Research Project 2008-2011

    International Nuclear Information System (INIS)

    2013-07-01

    The International Atomic Energy Agency (IAEA) supports Member State activities in the area of advanced fast reactor technology development by providing a forum for information exchange and collaborative research programmes. The Agency's activities in this field are mainly carried out within the framework of the Technical Working Group on Fast Reactors (TWG-FR), which assists in the implementation of corresponding IAEA activities and ensures that all technical activities are in line with the expressed needs of Member States. Among its broad range of activities, the IAEA proposes and establishes coordinated research projects (CRPs) aimed at the improvement of Member State capabilities in the area of fast reactor design and analysis. An important opportunity to undertake collaborative research was provided by the experimental campaign of the French Alternative Energies and Atomic Energy Commission (CEA) in the prototype sodium fast reactor PHENIX before it was shut down in 2009. The overall purpose of the end of life tests was to gather additional experience on the operation of sodium cooled reactors. As the CEA opened the experiments to international cooperation, in 2007 the IAEA launched a CRP on ''Control Rod Withdrawal and Sodium Natural Circulation Tests Performed during the PHENIX End-of-Life Experiments''. The CRP, with the participation of institutes from eight countries, contributed to improving capabilities in sodium cooled reactor simulation through code verification and validation, with particular emphasis on temperature and power distribution calculations and the analysis of sodium natural circulation phenomena. The objective of this report is to document the results and main achievements of the benchmark analyses on the natural circulation test performed in the framework of the PHENIX end of life experimental campaign

  17. The development of fast reactors in France - February 1982 to February 1983

    International Nuclear Information System (INIS)

    Vautrey, L.

    1983-01-01

    The report gives a general review of the development of fast reactors in France from February 1982 to February 1983, that is, the achievements of the last 12 months in what concerns Rapsodie, Phenix, Super Phenix 1 (the plant of Creys Malville), the studies of the project 1500 (Super Phenix 2) and the perspectives of the future. The essential points are the following: (1) The French electronuclear program actually follows the one defined by the Government in the fall of 1981. (2) The decision to definitely stop Rapsodie was taken last October. Some final experiments related to safety will be performed before the ultimate shutdown of the reactor. (3) The operating of Phenix has been disturbed by four leaks in the steam generator. The consequences were minimal. One proceeds successively to the change of the reheating systems on the three circuits. (4) The construction of the Creys Malville power plant is proceeding normally. (5) The studies for after Creys Malville follow their way: studies of the Project 1500 (Super Phenix 2) and of the fuel cycle installations. (6) Research and development, particularly oriented towards the needs of Super Phenix 1 and the perspectives of Super Phenix 2, keeps at a constant level. (7) International co-operation keeps a very important place. (8) The financial and personnel resources remain stable: about 1500 million francs for 1983, including the studies on the fuel cycle and safety, and excluding the operation of Phenix

  18. PHENIX WBS notes

    International Nuclear Information System (INIS)

    1994-02-01

    The Work Breakdown Structure (WBS) Book begins with this Overview section, which contains the high-level summary cost estimate, the cost profile, and the global construction schedule. The summary cost estimate shows the total US cost and the cost in terms of PHENIX construction funds for building the PHENIX detector. All costs in the WBS book are shown in FY 1993 dollars. Also shown are the institutional and foreign contributions, the level of pre-operations funding, and the cost of deferred items. Pie charts are presented at PHENIX WBS level 1 and 2 that show this information. The PHENIX construction funds are shown broken down to PHENIX WBS level 3 items per fiscal year, and the resulting profile is compared to the RHIC target profile. An accumulated difference of the two profiles is also shown. The PHENIX global construction schedule is presented at the end of the Overview section. Following the Overview are sections for each subsystem. Each subsystem section begins with a summary cost estimate, cost profile, and critical path. The total level 3 cost is broken down into fixed costs (M ampersand S), engineering costs (EDIA) and labor costs. Costs are further broken down in terms of PHENIX construction funds, institutional and foreign contributions, pre-operations funding, and deferred items. Also shown is the contingency at level 3 and the level 4 breakdown of the total cost. The cost profile in fiscal years is shown at level 3. The subsystem summaries are followed by the full cost estimate and schedule sheets for that subsystem. These detailed sheets are typically carried down to level 7 or 8. The cost estimate Total, M ampersand S, EDIA, and Labor breakdowns, as well as contingency, for each WBS entry

  19. Safety of confinement of Super Phenix: MARS test

    International Nuclear Information System (INIS)

    Falgayrettes, M.F.G.; Hamon, P.; Fiche, C.

    1984-08-01

    The protection of people and property must be assured by every situation around an industrial power plant. That is why the French Commissariat a l'Energie Atomique has defined the size of the confinement of Super Phenix to withstand the worst highly hypothetical accident. This report presents the study of the strength of the confinement carried out on a reactor mock-up. The latter is presented in film. The solution which have been adopted for the problem encountered are emphasized. Finally consequences are examined [fr

  20. From the Phenix irradiation end to the analytical results: PROFIL R target destructive characterization

    International Nuclear Information System (INIS)

    Ferlay, G.; Dancausse, J. Ph.

    2009-01-01

    In the French long-lived radionuclide (LLRN) transmutation program, several irradiation experiments were initiated in the Phenix fast neutron reactor to obtain a better understanding of the transmutation processes. The PROFIL experiments are performed in order to collect accurate information on the total capture integral cross sections of the principal heavy isotopes and some important fission products in the spectral range of fast reactors. One of the final goals is to diminish the uncertainties on the capture cross-section of the fission products involved in reactivity losses in fast reactors. This program includes two parts: PROFIL-R irradiated in a standard fast reactor spectrum and PROFIL-M irradiated in a moderated spectrum. The PROFIL-R and PROFIL-M irradiations were completed in August 2005 and May 2008, respectively. For both irradiations more than a hundred containers with isotopes of pure actinides and other elements in different chemical forms must be characterized. This raises a technical and analytical challenge: how to recover by selective dissolution less than 5 mg of isotope powder from a container with dimensions of only a few millimeters using hot cell facilities, and how to determine analytically both trace and ultra-trace elemental and isotopic compositions with sufficient accuracy to be useful for code calculations. (authors)

  1. PHENIX Work Breakdown Structure

    International Nuclear Information System (INIS)

    1994-02-01

    The Work Breakdown Structure (WBS) Book begins with this Overview section, which contains the high-level summary cost estimate, the cost profile, and the global construction schedule. The summary cost estimate shows the total US cost and the cost in terms of PHENIX construction funds for building the PHENIX detector. All costs in the WBS book are shown in FY 1993 dollars. Also shown are the institutional and foreign contributions, the level of pre-operations funding, and the cost of deferred items. Pie charts are presented at PHENIX WBS level 1 and 2 that show this information. The PHENIX construction funds are shown broken down to PHENIX WBS level 3 items per fiscal year, and the resulting profile is compared to the RHIC target profile. An accumulated difference of the two profiles is also shown. The PHENIX global construction schedule is presented at the end of the Overview section. Following the Overview are sections for each subsystem. Each subsystem section begins with a summary cost estimate, cost profile, and critical path. The total level 3 cost is broken down into fixed costs (M ampersand S), engineering costs (EDIA) and labor costs. Costs are further broken down in terms of PHENIX construction funds, institutional and foreign contributions, pre-operations funding, and deferred items. Also shown is the contingency at level 3 and the level 4 breakdown of the total cost. The cost profile in fiscal years is shown at level 3. The subsystem summaries are followed by the full cost estimate and schedule sheets for that subsystem. These detailed sheets are typically carried down to level 7 or 8. The cost estimate shows Total, M ampersand S, EDIA, and Labor breakdowns, as well as contingency, for each WBS entry

  2. The French liquid metal fast breeder reactor programme

    International Nuclear Information System (INIS)

    Rapin, M.

    1980-01-01

    The strong French LMFBR development and the corresponding success obtained up to now show that there is no technical insuperable barrier to fast breeder construction. This satisfactory evolution is in fact the conjunction of a strong incentive due to the lack of other resources, a firm and permanent stand of the government, and an obstinate effort of all the teams involved in the LMFBR field. The changeover to industrial level should be helped by the simplicity of the French organization for fast breeder. Finally, the development of LMFBR on a larger scale is helped by international agreements through which the present French know-how can be put at the disposal of other partners, and the general knowledge can be improved by setting common R and D programmes. A quite successful example of such agreements is given by the German-French agreement, and we hope that new partners will join us soon. (orig.) [de

  3. Draft of the PHENIX Management Plan

    International Nuclear Information System (INIS)

    1994-01-01

    The PHENIX Management Plan provides the baselines and controls that the PHENIX and RHIC Projects will follow to meet the technical, cost, and schedule goals for the PHENIX detector at RHIC. This plan will be reviewed and updated as required, with revisions made by agreement among the signed participants

  4. French LMFBR's control rods experience and development

    International Nuclear Information System (INIS)

    Arnaud, G.; Guigon, A.; Verset, L.

    1983-06-01

    Since the last ten years, the French program has been, first of all, directed to the setting up, and then the development of, at once, the Phenix control rods, and next, the Super-Phenix ones. The vented pin design, with porous plug and sodium bonding, which allows the choices of large diameters, has been taken, since the Rapsodie experience was decisive. The absorber material is sintered, 10 B enriched, boron carbide. The can is made of 316 type stainless steel, stabilised, or not, with titanium. The experience gained in Phenix up to now is important, and deals with about six loads of control rods. Results confirm the validity of the design of the absorber pins. Some difficulties has been encountered for the guiding devices, due to the swelling of the steel. They have required design and material improvements. Such difficulties are discarded by a new design of the bearing, for the Super-Phenix control rods. The other parts of these rods, from the Primary Shut-Down System, are strictly derived from Phenix. The design of the rods from the Secondary Shut-Down System is rather different, but it's not the case for the design of the absorber pins: in many a way, they are derived from Phenix pins and from Rapsodie control rods. Both types of rods irradiation tests are in progress in Phenix [fr

  5. {sup 20}F power measurement for generation IV sodium fast reactors

    Energy Technology Data Exchange (ETDEWEB)

    Coulon, R.; Normand, S.; Michel, M.; Barbot, L.; Domenech, T.; Boudergui, K.; Bourbotte, J.M.; Kondrasovs, V.; Frelin-Labalme, A.M.; Hamrita, H. [CEA, LIST, Laboratoire Capteurs et Architectures Electroniques, F-91191 Gif-sur-Yvette (France); BAN, G. [ENSICAEN, 6 Boulevard Marechal Juin, F-14050 Caen Cedex 4 (France); Barat, E.; Dautremer, T.; Montagu, T.; Carrel, F. [CEA, LIST, Laboratoire Modelisation Simulation et Systemes, F-91191 Gif-sur-Yvette (France); Brau, H.P. [ICSM, Centre de Marcoule, BP 17171 F-30207 Bagnols sur Ceze (France); Dumarcher, V. [AREVA NP, SET, F-84500 Bollene (France); Portier, J.L. [Centrale PHENIX, Centre de Marcoule, Groupe Essais Statistiques, F-30207 Bagnols sur Ceze (France); Jousset, P. [CEA, LIST, Laboratoire Capteurs Diamant, F-91191 Gif-sur-Yvette (France); Saurel, N. [CEA, DAM, Laboratoire Mesure de Dechets et Expertise, F-21120 Is-sur-Tille, France.F-84500 Bollene (France)

    2010-07-01

    The Phenix nuclear power plant has been a French Sodium Fast Reactor (SFR) prototype producing electrical power between 1973 and 2010. The power was monitored using ex-core neutron measurements. This kind of measurement instantly estimates the power but needs to be often calibrated with the heat balance thermodynamic measurement. Large safety and security margins have then been set not to derive above the nominal operating point. It is important for future SFR to reduce this margin and working closer to the nominal operating point. This work deals with the use of delayed gamma to measure the power. The main activation product contained in the primary sodium coolant is the {sup 24}Na which is not convenient for neutron flux measurement due to its long decay period. The experimental study done at the Phenix reactor shows that the use of {sup 20}F as power tagging agent gives a fast and accurate power measurement closed to the thermal balance measurement thanks to its high energy photon emission (1.634 MeV) and its short decay period (11 s). (authors)

  6. PHENIX Conceptual Design Report

    International Nuclear Information System (INIS)

    1993-01-01

    The PHENIX Conceptual Design Report (CDR) describes the detector design of the PHENIX experiment for Day-1 operation at the Relativistic Heavy Ion Collider (RHIC). The CDR presents the physics capabilities, technical details, cost estimate, construction schedule, funding profile, management structure, and possible upgrade paths of the PHENIX experiment. The primary goals of the PHENIX experiment are to detect the quark-gluon plasma (QGP) and to measure its properties. Many of the potential signatures for the QGP are measured as a function of a well-defined common variable to see if any or all of these signatures show a simultaneous anomaly due to the formation of the QGP. In addition, basic quantum chromodynamics phenomena, collision dynamics, and thermodynamic features of the initial states of the collision are studied. To achieve these goals, the PHENIX experiment measures lepton pairs (dielectrons and dimuons) to study various properties of vector mesons, such as the mass, the width, and the degree of yield suppression due to the formation of the QGP. The effect of thermal radiation on the continuum is studied in different regions of rapidity and mass. The eμ coincidence is measured to study charm production, and aids in understanding the shape of the continuum dilepton spectrum. Photons are measured to study direct emission of single photons and to study π 0 and η production. Charged hadrons are identified to study the spectrum shape, production of antinuclei, the φ meson (via K + K - decay), jets, and two-boson correlations. The measurements are made down to small cross sections to allow the study of high p T spectra, and J/ψ and Υ production. The PHENIX collaboration consists of over 300 scientists, engineers, and graduate students from 43 institutions in 10 countries. This large international collaboration is supported by US resources and significant foreign resources

  7. Optimization of FBR fuel element for high burnup

    International Nuclear Information System (INIS)

    Marbach, G.; Millet, P.

    1985-03-01

    After a brief historical background showing evolution of the French fast reactor fuel element from RAPSODIE to PHENIX and SUPER PHENIX we have examined the main points which have permitted to increase irradiation performance of the subassembly

  8. PHENIX Conceptual Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Nagamiya, Shoji; Aronson, Samuel H.; Young, Glenn R.; Paffrath, Leo

    1993-01-29

    The PHENIX Conceptual Design Report (CDR) describes the detector design of the PHENIX experiment for Day-1 operation at the Relativistic Heavy Ion Collider (RHIC). The CDR presents the physics capabilities, technical details, cost estimate, construction schedule, funding profile, management structure, and possible upgrade paths of the PHENIX experiment. The primary goals of the PHENIX experiment are to detect the quark-gluon plasma (QGP) and to measure its properties. Many of the potential signatures for the QGP are measured as a function of a well-defined common variable to see if any or all of these signatures show a simultaneous anomaly due to the formation of the QGP. In addition, basic quantum chromodynamics phenomena, collision dynamics, and thermodynamic features of the initial states of the collision are studied. To achieve these goals, the PHENIX experiment measures lepton pairs (dielectrons and dimuons) to study various properties of vector mesons, such as the mass, the width, and the degree of yield suppression due to the formation of the QGP. The effect of thermal radiation on the continuum is studied in different regions of rapidity and mass. The e[mu] coincidence is measured to study charm production, and aids in understanding the shape of the continuum dilepton spectrum. Photons are measured to study direct emission of single photons and to study [pi][sup 0] and [eta] production. Charged hadrons are identified to study the spectrum shape, production of antinuclei, the [phi] meson (via K[sup +]K[sup [minus

  9. First results from RHIC-PHENIX

    CERN Document Server

    Ghosh, T K; Adler, S S; Ajitanand, N N; Akiba, Y; Alexander, J; Aphecetche, L; Arai, Y; Aronson, S H; Averbeck, R; Awes, T C; Barish, K N; Barnes, P D; Barrette, J; Bassalleck, B; Bathe, S; Baublis, V; Bazilevsky, A; Belikov, S V; Bellaiche, F G; Belyaev, S T; Bennett, M J; Berdnikov, Yu A; Botelho, S S; Brooks, M L; Brown, D S; Bruner, N L; Bucher, D; Büsching, H; Bunce, G M; Burward-Hoy, J M; Butsyk, S; Carey, T A; Chand, P; Chang, J; Chang, W C; Chavez, L L; Chernichenko, S K; Chi, C Y; Chiba, J; Chiu, M; Choudhury, R K; Christ, T; Chujo, T; Chung, M S; Chung, P; Cianciolo, V; Cole, B A; D'Enterria, D G; Dávid, G; Delagrange, H; Denisov, A; Deshpande, A A; Desmond, E J; Dietzsch, O; Dinesh, B V; Drees, A; Durum, A A; Dutta, D; Ebisu, K; Efremenko, Yu V; Chenawi, K E; En-Yo, H; Esumi, S C; Ewell, L A; Ferdousi, T; Fields, D E; Fokin, S L; Fraenkel, Zeev; Franz, A; Frawley, A D; Fung, S Y; Garpman, S; Ghosh, T K; Glenn, A; Godoi, A L; Goto, Y; Greene, S V; Grosse-Perdekamp, M; Gupta, S K; Guryn, W; Gustafsson, Hans Åke; Haggerty, J S; Hamagaki, H; Hansen, A G; Hara, H; Hartouni, E P; Havano, R; Hayashi, N; He, X; Hemmick, T K; Heuser, J M; Hill, J C; Ho, D S; Homma, K; Hong, B; Hoover, A; Ichihara, T; Imai, K; Ippolitov, M S; Ishihara, M; Jacak, B V; Jang, W Y; Jia, J; Johnson, B M; Johnson, S C; Joo, K S; Kametani, S; Kang, J H; Kann, M; Kapoor, S S; Kelly, S; Khachaturov, B A; Khanzadeev, A V; Kikuchi, J; Kim, D J; Kim, H J; Kim, S Y; Kim, Y G; Kinnison, W W; Kistenev, E P; Kiyomichi, A; Klein-Bösing, C; Klinksiek, S A; Kochenda, L M; Kochetkov, D; Kochetkov, V; Köhler, D; Kohama, T; Kozlov, A; Kroon, P J; Kurita, K; Kweon, M J; Kwon, Y; Kyle, G S; Lacey, R A; Lajoie, J G; Lauret, J; Lebedev, A; Lee, D M; Leitch, M J; Li, X H; Li, Z; Lim, D J; Liu, M X; Liu, X; Liu, Z; Maguire, C F; Mahon, J; Makdisi, Y I; Man'ko, V I; Mao, Y; Mark, S K; Markacs, S; Martínez, G; Marx, M D; Massaike, A; Matathias, F; Matsumoto, T; McGaughey, P L; Melnikov, E A; Merschmeyer, M; Messer, F; Messer, M; Miake, Y; Miller, T E; Milov, A; Mioduszewski, S; Mischke, R E; Mishra, G C; Mitchell, J T; Mohanty, A K; Morrison, D P; Moss, J M; Muhlbacher, F; Muniruzzaman, M; Murata, J; Nagamiya, S; Nagasaka, Y; Nagle, J L; Nakada, Y; Nandi, B K; Newby, J; Nikkinen, L; Nilsson, P O; Nishimura, S; Nyanin, A S; Nystrand, J; O'Brien, E; Ogilvie, C A; Ohnishi, H; Ojha, I D; Ono, M; Onuchin, V A; Oskarsson, A; Österman, L; Otterlund, I; Oyama, K; Paffrath, L; Palounek, A P T; Pantuev, V S; Papavassiliou, V; Pate, S F; Peitzmann, Thomas; Petridis, A N; Pinkenburg, C H; Pisani, R P; Pitukhin, P; Plasil, F; Pollack, M E; Pope, K; Purschke, M L; Ravinovich, I; Read, K F; Reygers, K; Riabov, V; Riabov, Y; Rosati, M; Rose, A A; Ryu, S S; Saitô, N; Sakaguchi, A; Sakaguchi, T; Sako, H; Sakuma, T; Samsonov, V; Sangster, T C; Santo, R; Sato, H D; Sato, S; Sawada, S; Schlei, B R; Schutz, Y; Semenov, V; Seto, R; Shea, T K; Shein, I; Shibata, T A; Shigaki, K; Shiina, T; Shin, Y H; Sibiryak, Yu; Silvermyr, D; Sim, K S; Simon-Gillo, J; Singh, C P; Singh, V; Sivertz, M; Soldatov, A; Soltz, R A; Sørensen, S; Stankus, P W; Starinsky, N; Steinberg, P; Stenlund, E; Ster, A; Stoll, S P; Sugioka, M; Sugitate, T; Sullivan, J P; Sumi, Y; Sun, Z; Suzuki, M; Takagui, E M; Taketani, A; Tamai, M; Tanaka, Y; Taniguchi, E; Tannenbaum, M J; Thomas, J; Thomas, J H; Thomas, T L; Tian, W; Tojo, J; Torii, H A; Towell, R S; Tserruya, Itzhak; Tsuruoke, H; Tsvetkov, A A; Tuli, S K; Tydesjo, H; Tyurin, N; Ushiroda, T; van Hecke, H; Velissaris, C; Velkovska, J; Velkovsky, M; Vingradov, A A; Volkov, M A; Vorobyov, A A; Vznuzdaev, E A; Wang, H; Watanabe, Y; White, S N; Witzig, C; Wohn, F K; Woody, C L; Xie, W; Yagi, K; Yokkaichi, S; Young, G R; Yushmanov, I E; Zajc, W A; Zhang, Z; Zhou, S

    2001-01-01

    The PHENIX experiment consists of a large detector system located at the newly commissioned Relativistic Heavy Ion Collider (RHIC) at the Brookhaven National Laboratory. The primary goal of the PHENIX experiment is to look for signatures of the QCD prediction of a deconfined high-energy-density phase of nuclear matter and the quark gluon plasma. PHENIX started taking data for Au+Au collisions at square root (s/sub NN/)=130 GeV in June 2000. The signals from the beam-beam counter (BBC) and zero degree calorimeter (ZDC) are used to determine the centrality of the collision. A Glauber model reproduces the ZDC spectrum reasonably well to determine the participants in a collision. The charged particle multiplicity distribution from the first PHENIX paper is compared with the other RHIC experiment and the CERN and SPS results. Transverse momentum of photons are measured in the electro-magnetic calorimeter (EMCal) and preliminary results an presented. Particle identification is made by a time-of-flight (TOF) detecto...

  10. PHENIX reports. Final report

    International Nuclear Information System (INIS)

    1998-01-01

    The various tasks outlined in the Statement of Work for the PHENIX Program have been accomplished. Reports were generated which cover the work done. This report is a compilation of the following reports: Progress Report for May 1998; Progress Report for April 1998; PHENIX FEA Mount/Electron Shield Structural Analysis report; Progress Report for February 1998; Progress Report for March 1998; and Progress Report for December 1997 and January 1998

  11. Delayed gamma power measurement for sodium-cooled fast reactors

    Energy Technology Data Exchange (ETDEWEB)

    Coulon, R., E-mail: romain.coulon@cea.f [CEA, LIST, Laboratoire Capteurs et Architectures Electroniques, F-91191 Gif-sur-Yvette (France); Normand, S., E-mail: stephane.normand@cea.f [CEA, LIST, Laboratoire Capteurs et Architectures Electroniques, F-91191 Gif-sur-Yvette (France); Ban, G., E-mail: ban@lpccaen.in2p3.f [ENSICAEN, 6 Boulevard Marechal Juin, F-14050 Caen Cedex 4 (France); Barat, E.; Montagu, T.; Dautremer, T. [CEA, LIST, Laboratoire Modelisation Simulation et Systemes, F-91191 Gif-sur-Yvette (France); Brau, H.-P. [ICSM, Centre de Marcoule, BP 17171 F-30207 Bagnols sur Ceze (France); Dumarcher, V. [AREVA NP, SET, F-84500 Bollene (France); Michel, M.; Barbot, L.; Domenech, T.; Boudergui, K.; Bourbotte, J.-M. [CEA, LIST, Laboratoire Capteurs et Architectures Electroniques, F-91191 Gif-sur-Yvette (France); Jousset, P. [CEA, LIST, Departement des Capteurs, du Signal et de l' Information, F-91191 Gif-sur-Yvette (France); Barouch, G.; Ravaux, S.; Carrel, F. [CEA, LIST, Laboratoire Modelisation Simulation et Systemes, F-91191 Gif-sur-Yvette (France); Saurel, N. [CEA, DAM, Laboratoire Mesure de Dechets et Expertise, F-21120 Is-sur-Tille (France); Frelin-Labalme, A.-M.; Hamrita, H. [CEA, LIST, Laboratoire Capteurs et Architectures Electroniques, F-91191 Gif-sur-Yvette (France)

    2011-01-15

    Graphical abstract: Display Omitted Research highlights: {sup 20}F and {sup 23}Ne tagging agents are produced by fast neutron flux. {sup 20}F signal has been measured at the SFR Phenix prototype. A random error of only 3% for an integration time of 2 s could be achieved. {sup 20}F and {sup 23}Ne power measurement has a reduced temperature influence. Burn-up impact could be limited by simultaneous {sup 20}F and {sup 23}Ne measurement. - Abstract: Previous works on pressurized water reactors show that the nitrogen 16 activation product can be used to measure thermal power. Power monitoring using a more stable indicator than ex-core neutron measurements is required for operational sodium-cooled fast reactors, in order to improve their economic efficiency at the nominal operating point. The fluorine 20 and neon 23 produced by (n,{alpha}) and (n,p) capture in the sodium coolant have this type of convenient characteristic, suitable for power measurements with low build-up effects and a potentially limited temperature, flow rate, burn-up and breeding dependence. This method was tested for the first time during the final tests program of the French Phenix sodium-cooled fast reactor at CEA Marcoule, using the ADONIS gamma pulse analyzer. Despite a non-optimal experimental configuration for this application, the delayed gamma power measurement was pre-validated, and found to provide promising results.

  12. Towards automated crystallographic structure refinement with phenix.refine

    Energy Technology Data Exchange (ETDEWEB)

    Afonine, Pavel V., E-mail: pafonine@lbl.gov; Grosse-Kunstleve, Ralf W.; Echols, Nathaniel; Headd, Jeffrey J.; Moriarty, Nigel W. [Lawrence Berkeley National Laboratory, One Cyclotron Road, MS64R0121, Berkeley, CA 94720 (United States); Mustyakimov, Marat; Terwilliger, Thomas C. [Los Alamos National Laboratory, M888, Los Alamos, NM 87545 (United States); Urzhumtsev, Alexandre [CNRS–INSERM–UdS, 1 Rue Laurent Fries, BP 10142, 67404 Illkirch (France); Université Henri Poincaré, Nancy 1, BP 239, 54506 Vandoeuvre-lès-Nancy (France); Zwart, Peter H. [Lawrence Berkeley National Laboratory, One Cyclotron Road, MS64R0121, Berkeley, CA 94720 (United States); Adams, Paul D. [Lawrence Berkeley National Laboratory, One Cyclotron Road, MS64R0121, Berkeley, CA 94720 (United States); University of California Berkeley, Berkeley, CA 94720 (United States)

    2012-04-01

    phenix.refine is a program within the PHENIX package that supports crystallographic structure refinement against experimental data with a wide range of upper resolution limits using a large repertoire of model parameterizations. This paper presents an overview of the major phenix.refine features, with extensive literature references for readers interested in more detailed discussions of the methods. phenix.refine is a program within the PHENIX package that supports crystallographic structure refinement against experimental data with a wide range of upper resolution limits using a large repertoire of model parameterizations. It has several automation features and is also highly flexible. Several hundred parameters enable extensive customizations for complex use cases. Multiple user-defined refinement strategies can be applied to specific parts of the model in a single refinement run. An intuitive graphical user interface is available to guide novice users and to assist advanced users in managing refinement projects. X-ray or neutron diffraction data can be used separately or jointly in refinement. phenix.refine is tightly integrated into the PHENIX suite, where it serves as a critical component in automated model building, final structure refinement, structure validation and deposition to the wwPDB. This paper presents an overview of the major phenix.refine features, with extensive literature references for readers interested in more detailed discussions of the methods.

  13. Application of artificial intelligence to the detection and diagnosis of core faults in fast reactors

    International Nuclear Information System (INIS)

    Le Guillou, G.; Berlin, C.; Parcy, J.P.

    1983-01-01

    An automatic diagnostic system designed specially for fuel assembly accidents in fast reactors of the French type is described. It has an ''expert system'' structure and, at the present stage of the project, is operating on a laboratory scale in an experimental unit (Solar 16/65). The software aspects of the development of such systems (structure and formulation of rules, language, etc.) are presented in detail. Various simulation tests are outlined. ''Real-time'' application of the system will begin in 1983 on the Phenix reactor. (author)

  14. Modeling of Phenix End-of-Life control rod withdrawal benchmark with DYN3D SFR version

    Energy Technology Data Exchange (ETDEWEB)

    Nikitin, Evgeny; Fridman, Emil [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Reactor Safety

    2017-06-01

    The reactor dynamics code DYN3D is currently under extension for Sodium cooled Fast Reactor applications. The control rod withdrawal benchmark from the Phenix End-of-Life experiments was selected for verification and validation purposes. This report presents some selected results to demonstrate the feasibility of using DYN3D for steady-state Sodium cooled Fast Reactor analyses.

  15. The development of fast neutron reactors in France

    International Nuclear Information System (INIS)

    Petit, J.

    1983-01-01

    The French strategy is based on a coherent and carefully defined development program launched in 1950, each new stage of which is decided upon after the results of the preceding stage are analyzed. Rapsodie, the forst experimental reactor began operating in 1967 after more than 10 years of full scale test of its components. The in-pile fuel and component behaviour experience gained was put to immediate use for the design and out-of-pile tests of components for Phenix. Phenix is a prototype power generating demonstration reactor which has been operating since 1974. Rapsodie was developed for rigorous and statistical test of fuel behaviour. Super Phenix, the 1200 MWe reactor of the Creys Malville plant was ordered in 1977 and benefited from the 3 years operating experience gained with Phenix and the 10 years of operating experience acquired with Rapsodie. In 1986, after only one year of experience with Super Phenix, it is expected that all the parties involved in the financial and technical aspects of Super Phenix will be in the position to suggest the next stage in the development of large commercial plants to the government. The next reactor in the series, Super Phenix 2, is currently being studied

  16. Update on the Futurix-FTA experiment in Phenix

    International Nuclear Information System (INIS)

    Jaecki, P.; Pillon, S.; Warin, D.; Donnet, L.; Hayes, S.L.; Kennedy, J.R.; Pasamehmetoglu, K.; Voit, S.L.; Haas, D.; Fernandez, A.; Arai, Y.

    2007-01-01

    Full text of publication follows. In support of the European and American programmes to investigate the use of nuclear reactors and accelerator-driven systems for transmutation of transuranic elements recovered from spent nuclear fuels, a joint irradiation test, named FUTURIX-FTA, is planned for the last two power cycles of the Phenix fast reactor. The objective of the experiment is to provide important data on the fast-spectrum irradiation performance of oxide, nitride, metallic and cermet fuels loaded with very high concentrations of plutonium, neptunium and americium. Both uranium-bearing and uranium-free compositions are included in the experimental test matrix, as well as helium and sodium-bonded fuel pin designs. The eight fuel compositions to be included in FUTURIX-FTA are shown. (authors)

  17. Complementary safety evaluation of the Phenix power station (INB n 71) in the light of the Fukushima power station accident

    International Nuclear Information System (INIS)

    2011-01-01

    This report proposes a complementary safety evaluation of the Phenix power station, one of the French basic nuclear installations (BNI, in French INB) in the light of the Fukushima accident. This evaluation takes the following risks into account: risks of flooding, earthquake, loss of power supply and loss of cooling, in addition to operational management of accident situations. It presents some characteristics of the Phenix installation (location, operator, industrial environment, installation characteristics), identifies the risks of cliff effect and the main structures and equipment, evaluates the seismic risk (installation sizing, installation conformity, margin evaluation), evaluates the flooding risk (installation sizing, installation conformity, margin evaluation), briefly examines other extreme natural phenomena (extreme meteorological conditions related to flooding, earthquake or flooding with a higher level than that for which the installation is designed). It analyzes the risk of a loss of power supply and of cooling (loss of external and internal electric sources, loss of the ultimate cooling system). It analyzes the management of severe accidents: crisis management organization, available intervention means, robustness of available means. It discusses the conditions of the use of subcontractors

  18. Fuel management codes for fast reactors

    International Nuclear Information System (INIS)

    Sicard, B.; Coulon, P.; Mougniot, J.C.; Gouriou, A.; Pontier, M.; Skok, J.; Carnoy, M.; Martin, J.

    The CAPHE code is used for managing and following up fuel subassemblies in the Phenix fast neutron reactor; the principal experimental results obtained since this reactor was commissioned are analyzed with this code. They are mainly concerned with following up fuel subassembly powers and core reactivity variations observed up to the beginning of the fifth Phenix working cycle (3/75). Characteristics of Phenix irradiated fuel subassemblies calculated by the CAPHE code are detailed as at April 1, 1975 (burn-up steel damage)

  19. The sPHENIX Experiment

    Science.gov (United States)

    Pérez Lara, Carlos E.

    2018-02-01

    Our understanding of QCD under extreme conditions has advanced tremendously in the last 20 years with the discovery of the Quark Gluon Plasma and its characterisation in heavy ion collisions at RHIC and LHC. The sPHENIX detector planned at RHIC is designed to further study the microscopic nature of the QGP through precision measurements of jet, upsilon and open heavy flavor probes over a broad pT range. The multi-year sPHENIX physics program will commence in early 2023, using state-of-the art detector technologies to fully exploit the highest RHIC luminosities. The experiment incorporates the 1.4 T former BaBar solenoid magnet, and will feature high precision tracking and vertexing capabilities, provided by a compact TPC, Si-strip intermediate tracker and MAPS vertex detector. This is complemented by highly granular electromagnetic and hadronic calorimetry with full azimuthal coverage. In this document I describe the sPHENIX detector design and physics program, with particular emphasis on the comprehensive open heavy flavour program enabled by the experiment's large coverage, high rate capability and precision vertexing.

  20. Phenix: A Reprocessing and Multiple Recycling Experiment Unique in the World

    International Nuclear Information System (INIS)

    Guidez, J.

    2013-01-01

    Fast reactor fuel cycle principle: The Phenix fresh fuel is MOX with about 20% of Plutonium, and 80% of uranium. It can be natural or even depleted uranium. After reprocessing of this burned fuel, you obtain more plutonium(surgenerator). If you use this plutonium with depleted uranium, you can produce new MOX for the reactor. And again… at the end you operate the plant, burning only natural and depleted uranium

  1. High cycle thermal fatigue: benchmark at a Te junction piping system of the nuclear power plant Phenix; Fatigue a grand nombre de cycles: benchmark d'un te de tuyauterie de la centrale Phenix

    Energy Technology Data Exchange (ETDEWEB)

    Gelineau, O.; Simoneau, J.P. [NOVATOME, a Div. of Framatome, 69 - Lyon (France); Roubin, P. [CEA Cadarache, DER, 13 - Saint-Paul-lez-Durance (France)

    2001-07-01

    This paper presents the studies of the benchmark concerning a high cycle thermal fatigue problem. This benchmark is based on an industrial case, a Te junction piping system of the french FBR Phenix. The main objectives were the comparison of the different methods used by the participants and the analysis of the damage evaluation methods capacity compared to the observed phenomena. This study took place in an international framework with the United Kingdom, Italy, Japan, Korea, Russia, India and France. (A.L.B.)

  2. Phenix Power Plant Decommissioning Project. Treatment of the Primary Cold Trap

    International Nuclear Information System (INIS)

    Deluge, M.

    2008-01-01

    Phenix is a sodium-cooled fast neutron reactor located at the CEA's Rhone Valley Center where it was commissioned in 1974. It has an electric power rating of 250 MW and is operated jointly by the CEA and EDF. Its primary role today is to investigate the transmutation of long-lived radioactive waste into shorter-lived wasteform. Its final shutdown is scheduled for the beginning of 2009. In this context the Phenix Power Plant Decommissioning Project was initiated in 2003. It covers the definitive cessation of plant operation and the dismantling (D and D) operations together with the final shutdown preparatory phase. The final shutdown phase includes the operations authorized within the standard operating methodological framework. The dismantling phase also comprises treatment of sodium-bearing waste and dismantling of the nuclear facilities (reactor block, shielded cells, etc.). Treatment of the Phenix primary cold trap is scheduled to begin in 2016. The analysis program includes the following steps: - Accurately determine the contamination in the trap by carrying out gamma spectrometry measurement campaigns from 2007 to 2013 (the remaining difficulty will be to accurately determine the distribution of the contamination). - Validate the safety studies for the ELA facility. This work is currently in progress; ELA will be commissioned following inactive qualification testing. - Proceed with cutting tests on the knit mesh filter, which are scheduled to begin in 2008

  3. Embrittlement of a 17Cr ferritic steel irradiated in Phenix

    International Nuclear Information System (INIS)

    Allegraud, G.; Boutard, J.L.; Boyer, J.M.

    1987-01-01

    Charpy V and tensile tests have been performed with samples made of 17Cr ferritic steel irradiated in Phenix at temperatures between 390 and 540C up to a maximum dose of 83.3 dpaF. All over the temperature and dose ranges, irradiation leads to an increase of the ductile brittle transition temperature (DBTT). The DBTT and hardening are decreasing functions of the irradiation temperature. Fast neutron flux at 390C hardens the material more than a sole thermal ageing does

  4. PHENIX WBS notes. Cost and schedule review copy

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    The Work Breakdown Structure (WBS) Book begins with this Overview section, which contains the high-level summary cost estimate, the cost profile, and the global construction schedule. The summary cost estimate shows the total US cost and the cost in terms of PHENIX construction funds for building the PHENIX detector. All costs in the WBS book are shown in FY 1993 dollars. Also shown are the institutional and foreign contributions, the level of pre-operations funding, and the cost of deferred items. Pie charts are presented at PHENIX WBS level 1 and 2 that show this information. The PHENIX construction funds are shown broken down to PHENIX WBS level 3 items per fiscal year, and the resulting profile is compared to the RHIC target profile. An accumulated difference of the two profiles is also shown. The PHENIX global construction schedule is presented at the end of the Overview section. Following the Overview are sections for each subsystem. Each subsystem section begins with a summary cost estimate, cost profile, and critical path. The total level 3 cost is broken down into fixed costs (M&S), engineering costs (EDIA) and labor costs. Costs are further broken down in terms of PHENIX construction funds, institutional and foreign contributions, pre-operations funding, and deferred items. Also shown is the contingency at level 3 and the level 4 breakdown of the total cost. The cost profile in fiscal years is shown at level 3. The subsystem summaries are followed by the full cost estimate and schedule sheets for that subsystem. These detailed sheets are typically carried down to level 7 or 8. The cost estimate Total, M&S, EDIA, and Labor breakdowns, as well as contingency, for each WBS entry.

  5. Automated Structure Solution with the PHENIX Suite

    Energy Technology Data Exchange (ETDEWEB)

    Zwart, Peter H.; Zwart, Peter H.; Afonine, Pavel; Grosse-Kunstleve, Ralf W.; Hung, Li-Wei; Ioerger, Tom R.; McCoy, A.J.; McKee, Eric; Moriarty, Nigel; Read, Randy J.; Sacchettini, James C.; Sauter, Nicholas K.; Storoni, L.C.; Terwilliger, Tomas C.; Adams, Paul D.

    2008-06-09

    Significant time and effort are often required to solve and complete a macromolecular crystal structure. The development of automated computational methods for the analysis, solution and completion of crystallographic structures has the potential to produce minimally biased models in a short time without the need for manual intervention. The PHENIX software suite is a highly automated system for macromolecular structure determination that can rapidly arrive at an initial partial model of a structure without significant human intervention, given moderate resolution and good quality data. This achievement has been made possible by the development of new algorithms for structure determination, maximum-likelihood molecular replacement (PHASER), heavy-atom search (HySS), template and pattern-based automated model-building (RESOLVE, TEXTAL), automated macromolecular refinement (phenix.refine), and iterative model-building, density modification and refinement that can operate at moderate resolution (RESOLVE, AutoBuild). These algorithms are based on a highly integrated and comprehensive set of crystallographic libraries that have been built and made available to the community. The algorithms are tightly linked and made easily accessible to users through the PHENIX Wizards and the PHENIX GUI.

  6. Automated structure solution with the PHENIX suite

    Energy Technology Data Exchange (ETDEWEB)

    Terwilliger, Thomas C [Los Alamos National Laboratory; Zwart, Peter H [LBNL; Afonine, Pavel V [LBNL; Grosse - Kunstleve, Ralf W [LBNL

    2008-01-01

    Significant time and effort are often required to solve and complete a macromolecular crystal structure. The development of automated computational methods for the analysis, solution, and completion of crystallographic structures has the potential to produce minimally biased models in a short time without the need for manual intervention. The PHENIX software suite is a highly automated system for macromolecular structure determination that can rapidly arrive at an initial partial model of a structure without significant human intervention, given moderate resolution, and good quality data. This achievement has been made possible by the development of new algorithms for structure determination, maximum-likelihood molecular replacement (PHASER), heavy-atom search (HySS), template- and pattern-based automated model-building (RESOLVE, TEXTAL), automated macromolecular refinement (phenix. refine), and iterative model-building, density modification and refinement that can operate at moderate resolution (RESOLVE, AutoBuild). These algorithms are based on a highly integrated and comprehensive set of crystallographic libraries that have been built and made available to the community. The algorithms are tightly linked and made easily accessible to users through the PHENIX Wizards and the PHENIX GUI.

  7. Prognosis and management of myocardial infarction: Comparisons between the French FAST-MI 2010 registry and the French public health database.

    Science.gov (United States)

    Massoullié, Grégoire; Wintzer-Wehekind, Jérome; Chenaf, Chouki; Mulliez, Aurélien; Pereira, Bruno; Authier, Nicolas; Eschalier, Alain; Clerfond, Guillaume; Souteyrand, Géraud; Tabassome, Simon; Danchin, Nicolas; Citron, Bernard; Lusson, Jean-René; Puymirat, Étienne; Motreff, Pascal; Eschalier, Romain

    2016-05-01

    Multicentre registries of myocardial infarction management show a steady improvement in prognosis and greater access to myocardial revascularization in a more timely manner. While French registries are the standard references, the question arises: are data stemming solely from the activity of French cardiac intensive care units (ICUs) a true reflection of the entire French population with ST-segment elevation myocardial infarction (STEMI)? To compare data on patients hospitalized for STEMI from two French registries: the French registry of acute ST-elevation or non-ST-elevation myocardial infarction (FAST-MI) and the Échantillon généraliste des bénéficiaires (EGB) database. We compared patients treated for STEMI listed in the FAST-MI 2010 registry (n=1716) with those listed in the EGB database, which comprises a sample of 1/97th of the French population, also from 2010 (n=403). Compared with the FAST-MI 2010 registry, the EGB database population were older (67.2±15.3 vs 63.3±14.5 years; P<0.001), had a higher percentage of women (36.0% vs 24.7%; P<0.001), were less likely to undergo emergency coronary angiography (75.2% vs 96.3%; P<0.001) and were less often treated in university hospitals (27.1% vs 37.0%; P=0.001). There were no significant differences between the two registries in terms of cardiovascular risk factors, comorbidities and drug treatment at admission. Thirty-day mortality was higher in the EGB database (10.2% vs 4.4%; P<0.001). Registries such as FAST-MI are indispensable, not only for assessing epidemiological changes over time, but also for evaluating the prognostic effect of modern STEMI management. Meanwhile, exploitation of data from general databases, such as EGB, provides additional relevant information, as they include a broader population not routinely admitted to cardiac ICUs. Copyright © 2016 Elsevier Masson SAS. All rights reserved.

  8. The Phenix Detector magnet subsystem

    International Nuclear Information System (INIS)

    Yamamoto, R.M.; Bowers, J.M.; Harvey, A.R.

    1995-01-01

    The PHENIX [Photon Electron New Heavy Ion Experiment] Detector is one of two large detectors presently under construction for RHIC (Relativistic Heavy Ion Collider) located at Brookhaven National Laboratory. Its primary goal is to detect a new phase of matter; the quark-gluon plasma. In order to achieve this objective, the PHENIX Detector utilizes a complex magnet subsystem which is comprised of two large magnets identified as the Central Magnet (CM) and the Muon Magnet (MM). Muon Identifier steel is also included as part of this package. The entire magnet subsystem stands over 10 meters tall and weighs in excess of 1900 tons (see Fig. 1). Magnet size alone provided many technical challenges throughout the design and fabrication of the project. In addition, interaction with foreign collaborators provided the authors with new areas to address and problems to solve. Russian collaborators would fabricate a large fraction of the steel required and Japanese collaborators would supply the first coil. This paper will describe the overall design of the PHENIX magnet subsystem and discuss its present fabrication status

  9. The Phenix Detector magnet subsystem

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, R.M.; Bowers, J.M.; Harvey, A.R. [Lawrence Livermore National Lab., CA (United States)] [and others

    1995-05-19

    The PHENIX [Photon Electron New Heavy Ion Experiment] Detector is one of two large detectors presently under construction for RHIC (Relativistic Heavy Ion Collider) located at Brookhaven National Laboratory. Its primary goal is to detect a new phase of matter; the quark-gluon plasma. In order to achieve this objective, the PHENIX Detector utilizes a complex magnet subsystem which is comprised of two large magnets identified as the Central Magnet (CM) and the Muon Magnet (MM). Muon Identifier steel is also included as part of this package. The entire magnet subsystem stands over 10 meters tall and weighs in excess of 1900 tons (see Fig. 1). Magnet size alone provided many technical challenges throughout the design and fabrication of the project. In addition, interaction with foreign collaborators provided the authors with new areas to address and problems to solve. Russian collaborators would fabricate a large fraction of the steel required and Japanese collaborators would supply the first coil. This paper will describe the overall design of the PHENIX magnet subsystem and discuss its present fabrication status.

  10. Rebirth of a control rod at the Phenix power plant

    International Nuclear Information System (INIS)

    De Carvalho, Corinne; Vignau, Bernard; Masson, Marc

    2007-01-01

    This paper outlines the operations involved in cleaning the control rod for the complementary shutdown system in the Phenix Power Plant, the French sodium-cooled fast reactor. The Phenix reactor is controlled by six control rods and a complementary shutdown system. The latter comprises a control rod and a mechanism maintaining the rod in position by means of an electromagnet. The electromagnet is continuously supplied with power and holds the rod control assembly in position by magnetisation on a plane circular surface made from pure iron. The bearing capacity of the mechanism on the rod was initially 80 daN with a rod weight of 26.3 daN. This deteriorated progressively over time. The bearing surface of the rod and the electromagnet became contaminated with a deposit of sodium oxides and metallic particles, thus creating an air gap. This reached a figure of 36 daN in 2005 and was deemed not to be sufficient to prevent the rod from dropping at the wrong time during reactor operation. The Power Plant thus decided to replace the rod mechanism in the reactor in an initial phase, followed by the control rod itself. As the Phenix Power Plant had no spare control rods left, they initiated a 'salvage' plan, over two stages, for the rod removed from the reactor and placed in the fuel storage drum: - Inspection of the bearing surface of the rod by means of a borescope to check whether the rod could be salvaged, - A cleaning operation on the bearing face and checks on the bearing capacity of the rod. The operation is subject to very stringent requirements: the rod must not be taken out of the sodium to ensure that it can be reused in the reactor. The operation must thus take place in the fuel storage drum where there are no facilities for such an operation and where operating conditions are very hostile: high temperatures (the sodium in the fuel storage drum is at a temperature of 150 deg. C, high dose rate (3 mGy/h on the bearing surface) and the bearing surface is submerged

  11. Phenix: a story of core and energy

    International Nuclear Information System (INIS)

    Sauvage, J.F.

    2005-01-01

    Phenix is the name of a legendary bird which could have several successive lives thanks to a rebirth from its ashes. It is by analogy the name given to an original sodium-cooled fast breeder reactor capable to generate new quantities of energy using the by products of its core burnup. This book tells the story of this reactor: construction (1968-1974), first years of operation (1974-1980), success era (1980-1986), first problems (1986-1992), safety re-evaluation (1992-1998), renovation of the core (1998-2003), re-start up of operation (2003-2009). A description of the power plant is given in appendix: core, reactor vessel, circuits, handling, instrumentation and control, safety, buildings, operation. (J.S.)

  12. Breeder reactors

    International Nuclear Information System (INIS)

    Gollion, H.

    1977-01-01

    The reasons for the development of fast reactors are briefly reviewed (a propitious neutron balance oriented towards a maximum uranium burnup) and its special requirements (cooling, fissile material density and reprocessing) discussed. The three stages in the French program of fast reactor development are outlined with Rapsodie at Cadarache, Phenix at Marcoule, and Super Phenix at Creys-Malville. The more specific features of the program of research and development are emphasized: kinetics and the core, the fuel and the components [fr

  13. Mechanical behavior of a fast reactor core: Application of the 3D codes to SUPER PHENIX 1

    International Nuclear Information System (INIS)

    Bernard, A.; Masoni, P.; Dorsselaere, J.P. van

    1983-01-01

    The series of the 3-dimensional mechanical codes of a fast reactor core was used for the first time within the framework of a design study of an industrial reactor: SUPER-PHENIX 1. These codes are the following ones: - ARGOH which calculates the behavior of an isolated subassembly. - HARMONIE which calculates the core mechanical equilibrium - TRACAR which yields a graphic visualization of HARMONIE results, and calculates the handling forces and support reactions - HARMOREA which calculates the reactivity variations between given equilibrium states (for instance: pads effect and diagrid effect); now at the end of its development. The calculations were performed on 1/3 of the SPX1 core. Their purpose is double: - on the one hand, to check design criteria, and provide the loadings for the subassembly mechanical design studies; on the other hand, to evaluate the reactivity effects, related to the horizontal core deformations, and useful for operation and safety studies. The results of these calculations showed that the design criteria were verified for the contractual lifetime of the subassemblies. (orig.)

  14. PHENIX Work Breakdown Structure. Cost and schedule review copy

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    The Work Breakdown Structure (WBS) Book begins with this Overview section, which contains the high-level summary cost estimate, the cost profile, and the global construction schedule. The summary cost estimate shows the total US cost and the cost in terms of PHENIX construction funds for building the PHENIX detector. All costs in the WBS book are shown in FY 1993 dollars. Also shown are the institutional and foreign contributions, the level of pre-operations funding, and the cost of deferred items. Pie charts are presented at PHENIX WBS level 1 and 2 that show this information. The PHENIX construction funds are shown broken down to PHENIX WBS level 3 items per fiscal year, and the resulting profile is compared to the RHIC target profile. An accumulated difference of the two profiles is also shown. The PHENIX global construction schedule is presented at the end of the Overview section. Following the Overview are sections for each subsystem. Each subsystem section begins with a summary cost estimate, cost profile, and critical path. The total level 3 cost is broken down into fixed costs (M&S), engineering costs (EDIA) and labor costs. Costs are further broken down in terms of PHENIX construction funds, institutional and foreign contributions, pre-operations funding, and deferred items. Also shown is the contingency at level 3 and the level 4 breakdown of the total cost. The cost profile in fiscal years is shown at level 3. The subsystem summaries are followed by the full cost estimate and schedule sheets for that subsystem. These detailed sheets are typically carried down to level 7 or 8. The cost estimate shows Total, M&S, EDIA, and Labor breakdowns, as well as contingency, for each WBS entry.

  15. Operating experience with small diameter bellows used in the Phenix and Rapsodie reactors, and in sodium test facilities

    International Nuclear Information System (INIS)

    Allegre, P.; Jacquelin, R.; Carbonnier, J.L.

    1980-01-01

    In the Rapsodie and Phenix fast breeder reactors, small diameter bellows are used on the control rod mechanisms and on some valves. The Valve bellows sustain slow longitudinal movements with stroke/length ratios of about 0.3, and hydroformed bellows are suitable for this application. The control rod mechanism bellows are subjected to greater length variations (ΔL/L>0.5) including fast drops, so that welded disk models are used

  16. Design and fabrication procedures of Super-Phenix fuel elements

    International Nuclear Information System (INIS)

    Leclere, J.; Vialard, J.-L.; Delpeyroux, P.

    1975-01-01

    For Super-Phenix fuel assemblies, Phenix technological arrangements will be used again, but they will be simplified as far as possible. The maximum fuel can temperature has been lowered in order to obtain a good behavior of hexagonal tubes and cans at high irradiation levels. An important experimental programme and the experience gained from Phenix operation will confirm the merits of the options retained. The fuel element fabrication is envisaged to take place in the plutonium workshop at Cadarache. Usual procedures will be employed and both reliability and automation will be increased [fr

  17. Evolution of the roof insulation conception in French LMFBR

    International Nuclear Information System (INIS)

    Frachet, S.; Pradel, P.

    1986-01-01

    France has built two power producing fast breeders: the 250 MWe PHENIX and the 1200 MWe SUPER-PHENIX-1 (with European participation) and is presently working on the preliminary design of a third 1500 MWe reactor SUPER-PHENIX-2. The upper closures of these pool type reactors are essential structural elements since they fulfill several vital functions. The following points are briefly discussed in this paper: The different facilities which have contributed to validate the SPX1 and SPX2 upper-shuttings: Gulliver, Coca, Germinal; the numerical methods which were perfected to validate the calculation of the penetrations; a heat balance which is used to estimate the temperature of the cover gas; the solution adopted to avoid the aerosols deposits

  18. Global variables and identified hadrons in the PHENIX experiment

    Indian Academy of Sciences (India)

    verse momentum, mean transverse energy, and net charge are presented for particles ... Other talks at this conference summarized the PHENIX results for high pT charged ... The major goal of the heavy-ion program in PHENIX is to detect and.

  19. Sodium fast reactor power monitoring using gamma spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Coulon, R.; Normand, S.; Barbot, L.; Domenech, T.; Kondrasovs, V.; Corre, G.; Frelin, A.M. [CEA, LIST, Laboratoire Capteurs et Architectures Electroniques, CEA - Saclay DRT/LIST/DETECS/SSTM, Batiment 516 - P.C. no 72, Gif sur Yvette, F-91191 (France); Montagu, T.; Dautremer, T.; Barat, E. [CEA, LIST, Laboratoire Processus Stochastiques et Spectres (France); Ban, G. [ENSICAEN (France)

    2009-06-15

    This work deals with the use of high flux gamma spectrometry to monitor the fourth generation of sodium fast reactor (SFR) power. The simulation study part of this work has shown that power monitoring in a short time response and with a good accuracy is possible. An experimental test is under preparation at the French SFR Phenix experimental reactor to validate simulation studies. First, physical calculations have been done to correlate gamma activity to the released thermal power. Gamma emitter production rate in the reactor core was calculated with technical and nuclear data as the sodium velocity, the atomic densities, Phenix neutron spectrum and incident neutron cross-sections of reactions producing gamma emitters. A thermal hydraulic transfer function was used for modeling primary sodium flow in our calculations. For the power monitoring problematic, use of a short decay period gamma emitter will allow to have a very fast response system without cumulative effect. We have determined that the best tagging agent is 20F which emits 1634 keV energy photons with a decay period of 11 s. The gamma spectrum was determined by flux point and a pulse high tally MCNP5.1.40 simulation and shown the possibility to measure the signal of this radionuclide. The experiment will be set during the reactor 'end life testing'. The Delayed Neutron Detection (DND) room has been chosen as the best available location on Phenix reactor to measure this kind of radionuclide due to a short transit time from reactor core to measurement sample. This location is optimum for global power measurement because homogenized sampling in the reactor hot pool. The main spectrometer is composed of a coaxial high purity germanium diode (HPGe) coupled with a transistor reset preamplifier. The HPGe diode signal will be processed by the Adonis digital signal processing due to high flux and fast activity measurement. Post-processing softwares will be used to limit statistical problems of the

  20. IAEA coordinated research program on `harmonization and validation of fast reactor thermomechanical and thermohydraulic codes using experimental data`. 1. Thermohydraulic benchmark analysis on high-cycle thermal fatigue events occurred at French fast breeder reactor Phenix

    Energy Technology Data Exchange (ETDEWEB)

    Muramatsu, Toshiharu [Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center

    1997-06-01

    A benchmark exercise on `Tee junction of Liquid Metal Fast Reactor (LMFR) secondary circuit` was proposed by France in the scope of the said Coordinated Research Program (CRP) via International Atomic Energy Agency (IAEA). The physical phenomenon chosen here deals with the mixture of two flows of different temperature. In a LMFR, several areas of the reactor are submitted to this problem. They are often difficult to design, because of the complexity of the phenomena involved. This is one of the major problems of the LMFRs. This problem has been encountered in the Phenix reactor on the secondary loop, where defects in a tee junction zone were detected during a campaign of inspections after an operation of 90,000 hours of the reactor. The present benchmark is based on an industrial problem and deal with thermal striping phenomena. Problems on pipes induced by thermal striping phenomena have been observed in some reactors and experimental facilities coolant circuits. This report presents numerical results on thermohydraulic characteristics of the benchmark problem, carried out using a direct numerical simulation code DINUS-3 and a boundary element code BEMSET. From the analysis with both the codes, it was confirmed that the hot sodium from the small pipe rise into the cold sodium of the main pipe with thermally instabilities. Furthermore, it was indicated that the coolant mixing region including the instabilities agrees approximately with the result by eye inspections. (author)

  1. The development of fast reactors in France from March 1980 to March 1981; Le developpement des reacteurs a neutrons rapides en France de mars 1980 a mars 1981

    Energy Technology Data Exchange (ETDEWEB)

    Vautrey, L. [Commissariat a l' Energie Atomique, CEN de Saclay, Gif-sur-Yvette (France)

    1981-05-15

    This paper describes general features concerning development in the field of fast reactors in France from March 1980 to March 1981. It concentrates mainly on: Rapsodie, Phenix NPP, prototype reactor Super Phenix 1, future fast reactor NPPs and current research and development programs in the field. The present situation is as follows. Rapsodie has restarted operation but at reduced power in July 1980 because of the problems in the primary circuit which have not yet been solved. Phenic operates in a very satisfactory manner. Construction of Super Phenix is continuing normally. Research activities are performed sometimes for the needs of Super Phenix and sometimes for the needs of future fast rector projects like Super Phenix 2. International cooperation is being continued.

  2. Identification of Super Phenix steam generator by a simple polynomial model

    International Nuclear Information System (INIS)

    Rousseau, I.

    1981-01-01

    This note suggests a method of identification for the steam generator of the Super-Phenix fast neutron power plant for simple polynomial models. This approach is justified in the selection of the adaptive control. The identification algorithms presented will be applied to multivariable input-output behaviours. The results obtained with the representation in self-regressive form and by simple polynomial models will be compared and the effect of perturbations on the output signal will be tested, in order to select a good identification algorithm for multivariable adaptive regulation [fr

  3. Electronics for the RHIC PHENIX detector

    International Nuclear Information System (INIS)

    Young, G.R.

    1992-01-01

    The PHENIX detector for RHIC is being designed to measure lepton pairs, direct photons and hadrons emitted in collisions of heavy nuclei at center of mass energies up to 200 GeV/(nucleon-pair). The physics goal is tests of predictions concerning the existence and nature of a deconfined state of strongly-interacting matter. The relatively large final state multiplicities, which reach 1500 charged particles per unit of rapidity, place strong demands on detector segmentation and control of electronics cost and power consumption. An overview of present ideas concerning signal processing and data rates for PHENIX will be presented

  4. Intermediate heat exchanger project for Super Phenix

    International Nuclear Information System (INIS)

    Roumailhac, J.; Desir, D.

    1975-01-01

    The Super Phenix (1200 MWe) intermediate heat exchangers are derived directly from those of Phenix (250 MWe). The intermediate exchangers are housed in the reactor vessel annulus: as this annulus must be of the smallest volume possible, these IHX are required to work at a high specific rating. The exchange surface is calculated for nominal conditions. A range is then defined, consistent with the above requirements and throughout which the ratio between bundle thickness and bundle length remains acceptable. Experimental technics and calculations were used to determine the number of tube constraint systems required to keep the vibration amplitude within permissible limits. From a knowledge of this number, the pressure drop produced by the primary flow can be calculated. The bundle geometry is determined together with the design of the corresponding tube plates and the way in which these plates should be joined to the body of the IHX. The experience (technical and financial) acquired in the construction of Phenix is then used to optimize the design of the Super Phenix project. An approximate definition of the structure of the IHX is obtained by assuming a simplified load distribution in the calculations. More sophisticated calculations (e.g. finite element method) are then used to determine the behaviour of the different points of the IHX, under nominal and transient conditions

  5. Scenario for commercialization of fast breeder reactors

    International Nuclear Information System (INIS)

    Kumaoka, Yoshio; Sato, Morihiko

    1989-01-01

    To realize the commercialization of fast breeder reactors (FBRs), it is essential to reduce construction costs to the same level as those for the current light water reactors. For this target to be attained, a highly important factor is to reduce to the lowest-levels possible the quantities of materials and volume of the buildings required for the primary and secondary sodium loops of the FBR. In this direction, an innovative compact FBR plant concept which holds promise for commercialization has been developed by introducing the pooltype reactor concept with the shortest possible secondary sodium loops, realized by coupling electromagnetic pumps with the steam generators. In comparison with the French Super Phenix reactor, for example, the construction of this 1,300-MWe FBR plant could be achieved with half the material quantities and plant volume required by the former type. (author)

  6. High energy resolution and high count rate gamma spectrometry measurement of primary coolant of generation 4 sodium-cooled fast reactor

    International Nuclear Information System (INIS)

    Coulon, R.

    2010-01-01

    Sodium-cooled Fast Reactors are under development for the fourth generation of nuclear reactor. Breeders reactors could gives solutions for the need of energy and the preservation of uranium resources. An other purpose is the radioactive wastes production reduction by transmutation and the control of non-proliferation using a closed-cycle. These thesis shows safety and profit advantages that could be obtained by a new generation of gamma spectrometry system for SFR. Now, the high count rate abilities, allow us to study new methods of accurate power measurement and fast clad failure detection. Simulations have been done and an experimental test has been performed at the French Phenix SFR of the CEA Marcoule showing promising results for these new measurements. (author) [fr

  7. Fast reactor development program in France in 1997

    International Nuclear Information System (INIS)

    Langrand, J.C.; Hubert, G.; Marmonier, P.; Del Negro, R.; Saint-Arroman, G.; Coulon, P.; Mesnage, B.; Pillon, S.; Lefevre, J.C.

    1998-01-01

    The operating performance of the French nuclear plants in 1997 were again satisfactory, confirming the good 1996 results; 78% of the national electricity production was of nuclear origin (376/481 TWh); the nuclear safety indicators were even better with a slight decrease in the number of reported incidents; the availability factor was higher than 82,5%; the kWh production cost continue to decrease by about 1,7% per year; thanks to an ALARA approach, individual and collective doses are still decreasing; the liquid and gaseous releases are also still decreasing and the volume of nuclear wastes is equivalent to last year. The major event of 1997 was the confirmation for the start up of the most advanced nuclear plants, N4 type, with Chooz B1 reaching full power on May 9, 1997 and Chooz B2 following soon with first criticality on March 10 and full power on September 18. As a confirmation and enjoying the experience of Chooz B the first unit of Civaux was synchronised to the grid end of 1997 after fuel loading in Sept 1997. The status of fast reactors was deeply modified, with the governmental decision to abandon Superphenix, which led to decide to close also EFR studies in 1997, and the perspective of operating Phenix till 2004, mainly for studies on radioactive wastes incineration. Three meetings were held during the second half of the year by the > (GP - Permanent Committee) on Phenix; after reviewing all the safety aspects, they concluded to the possibility to resume operation according to the general following scheme: one cycle in 1998, about one year for works, then 6 cycles between 2000 and 2004. Of course, the main event concerning Superphenix is the decision of abandon announced in June 1997. The decree allowing operation had been cancelled in February. The works foreseen in the frame of the planned > shutdown had been conducted satisfactorily, during the first-half of the year. At the beginning of 1998, it was stated that the reactor would not operate again

  8. 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)

  9. Margarines and Fast-Food French Fries: Low Content of trans Fatty Acids.

    Science.gov (United States)

    Astiasarán, Iciar; Abella, Elena; Gatta, Giulia; Ansorena, Diana

    2017-06-28

    The lipid fraction of margarines and fast food French fries, two types of foods traditionally high in trans fatty acids (TFA), is assessed. TFA data reported worldwide during the last 20 years have been gathered and show that some countries still report high TFA amounts in these products. The content of TFA was analysed in margarines (two store and four premium brands) and French-fries from fast-food restaurants (five chains). All samples were collected in Pamplona (Navarra, Spain). The margarines showed mean values of 0.68% and 0.43% (g TFA/100 g fat) for the store and premium brands, respectively. The French fries' values ranged from 0.49% to 0.89%. All samples were lower than the 2% set by some European countries as the maximum legal content of TFA in fats, and contained less than 0.5 g/serving, so they could also be considered " trans free products". This work confirmed that the presence of TFA is not significant in the two analysed products and contributes updated food composition tables, key tools for epidemiological and nutrition studies.

  10. 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)

  11. Some safety related characteristics of Phenix, a 250 MWe fast reactor -1989 and 1990 negative reactivity trip investigations

    International Nuclear Information System (INIS)

    Chaumont, J.M.; Goux, D.; Martin, L.

    1993-01-01

    The main characteristics of the Phenix core control are summarized. The current state of the investigations related to the 1989 and 1990 negative reactivity transients are presented with emphasis on the results of the very low power tests recently performed. (authors). 5 figs., 2 refs

  12. Exploring forward physics with the PHENIX MPC-EX upgrade

    Science.gov (United States)

    Novitzky, Norbert; Phenix Collaboration

    2014-09-01

    The MPC-EX detector is a Si-W preshower extension to the existing Muon Piston Calorimeter (MPC) at PHENIX. Located at forward rapidity, 3 . 1 double showers. The single versus double shower separation was tested with an electron beam at the SLAC test beam facility. Results from the test beam data will be presented in this talk. The MPC-EX detector is a Si-W preshower extension to the existing Muon Piston Calorimeter (MPC) at PHENIX. Located at forward rapidity, 3 . 1 double showers. The single versus double shower separation was tested with an electron beam at the SLAC test beam facility. Results from the test beam data will be presented in this talk. Norbert Novitzky for PHENIX collaboration.

  13. Towards automated crystallographic structure refinement with phenix.refine

    OpenAIRE

    Afonine, Pavel V.; Grosse-Kunstleve, Ralf W.; Echols, Nathaniel; Headd, Jeffrey J.; Moriarty, Nigel W.; Mustyakimov, Marat; Terwilliger, Thomas C.; Urzhumtsev, Alexandre; Zwart, Peter H.; Adams, Paul D.

    2012-01-01

    phenix.refine is a program within the PHENIX package that supports crystallographic structure refinement against experimental data with a wide range of upper resolution limits using a large repertoire of model parameterizations. It has several automation features and is also highly flexible. Several hundred parameters enable extensive customizations for complex use cases. Multiple user-defined refinement strategies can be applied to specific parts of the model in a single refinement run. An i...

  14. Ferritic steels for French LMFBR steam generators

    International Nuclear Information System (INIS)

    Aubert, M.; Mathieu, B.; Petrequin, P.

    1983-06-01

    Austenitic stainless steels have been widely used in many components of the French LMFBR. Up to now, ferritic steels have not been considered for these components, mainly due to their relatively low creep properties. Some ferritic steels are usable when the maximum temperatures in service do not exceed about 530 0 C. It is the case of the steam generators of the Phenix plant, where the exchange tubes of the evaporator are made of 2,25% Cr-1% Mo steel, stabilized or not by addition of niobium. These ferritic alloys have worked successfully since the first steam production in October 1973. For the SuperPhenix power plant, an ''all austenitic stainless alloy'' apparatus has been chosen. However, for the future, ferritic alloys offer potential for use as alternative materials in the evaporators: low alloys steels type 2,25% Cr-1% Mo (exchange tubes, tube-sheets, shells), or at higher chromium content type 9% Cr-2% Mo NbV (exchange tubes) or 12M Cr-1% Mo-V (tube-sheets). Most of these steels have already an industrial background, and are widely used in similar applications. The various potential applications of these steels are reviewed with regards to the French LMFBR steam generators, indicating that some points need an effort of clarification, for instance the properties of the heterogeneous ferritic/austenitic weldments

  15. Pin clad strains in Phenix

    International Nuclear Information System (INIS)

    Languille, A.

    1979-07-01

    The Phenix reactor has operated for 4 years in a satisfactory manner. The first 2 sub-assembly loadings contained pins clad in solution treated 316. The principal pin strains are: diametral strain (swelling and irradiation creep), ovality and spiral bending of the pin (interaction of wire and pin cluster and wrapper). A pin cluster irradiated to a dose of 80 dpa F reached a pin diameter strain of 5%. This strain is principally due to swelling (low fission gas pressure). The principal parameters governing the swelling are instantaneous dose, time and temperature for a given type of pin cladding. Other types of steel are or will be irradiated in Phenix. In particular, cold-worked titanium stabilised 316 steel should contribute towards a reduction in the pin clad strains and increase the target burn-up in this reactor. (author)

  16. Tube tightness survey during Phenix steam generator operation

    International Nuclear Information System (INIS)

    Cambillard, E.

    1976-01-01

    Phenix steam generators are once-through vessels with single-wall heat-exchange tubes. This design means that any leakage of water into the sodium must be detected as quickly as possible so that the installation can be shut down before extensive damage occurs. The detection of water leaks in Phenix steam generators is based on measurement of the concentration in the sodium, of hydrogen produced by the sodium-water reaction. Since the various modules--evaporators, superheaters, and reheaters--have no free sodium surfaces, detection of hydrogen in argon is not used in Phenix steam generators. The measurement systems employ a probe made of nickel tubes 0.3 mm thick. Hydrogen in the sodium diffuses into a chamber kept under vacuum by an ion pump. The hydrogen pressure in the chamber is measured by a quadrupole mass spectrometer. The nine measurement systems (three per steam generator) are calibrated by injecting hydrogen into the sodium of the secondary circuits. The data-processing computer calculates the hydrogen concentration in the sodium from the spectrometer signals and the probe temperatures, which are not regulated in Phenix; it generates instructions that enable the operator to act if a leak appears. So far, no leaks have been detected. These systems also make it possible to determine rates of hydrogen diffusion caused by corrosion of the steel walls on the water side

  17. The transmutation of americium: the Ecrix experiments in Phenix; Transmutation de l'americium: les experiences ecrix dans Phenix

    Energy Technology Data Exchange (ETDEWEB)

    Garnier, J C; Schmidt, N [CEA Cadarache, Dept. d' Etudes des Combustibles (DEC/SESC), 13 - Saint-Paul-lez-Durance (France); Croixmarie, Y; Ottaviani, J P [CEA Cadarache, Dept. d' Etudes des Combustibles (DEC/SPUA), 13 - Saint-Paul-lez-Durance (France); Varaine, F; Saint Jean, C de [CEA Cadarache, Dept. d' Etudes des Reacteurs (DER/SPRC), 13 - Saint-Paul-lez-Durance (France)

    1999-07-01

    The first americium transmutation experiment in a specific target in PHENIX will occur with the ECRIX-B and ECRIX-H experiments. Beside material testing, the objective is also to represent a concept of transmutation whose specificity is to enhance the kinetics of transmutation by using a moderated spectrum. The moderator materials will be {sup 11}B{sub 4}C and CaH{sub 2} for ECRIX-B and ECRIXH respectively, the irradiation conditions have been predicted for both the neutronics and thermal. The targets (MgO-AmO{sub X} pellets) are manufactured in the ATALANTE laboratory and the design is performed according to the PHENIX operating conditions. (authors)

  18. Fast reactor development programme in France

    Energy Technology Data Exchange (ETDEWEB)

    Le Rigoleur, C [Direction des Reacteurs Nucleaires, CEA Centre d` Etudes de Cadarache, Saint-Paul-lez-Durance (France)

    1998-04-01

    First the general situation regarding production of electricity in France is briefly described. Then in the field of Fast Reactors, the main events of 1996 are presented. At the end of February 1996, the PHENIX reactor was ready for operation. After review meetings, the Safety Authority has requested safety improvements and technical demonstrations, before it examines the possibility of authorizing a new start-up of PHENIX. The year 1996 was devoted to this work. In 1996, SUPERPHENIX was characterized by excellent operation throughout the year. The reactor was restarted at the end of 1995 after a number of minor incidents. The reactor power was increased by successive steps: 30% Pn up to February 6, followed by 50% Pn up to May then 60% up to October and 90% Pn during the last months. A programmed shutdown period occurred during May, June and mid-July 1996. The reactor has been shutdown at the end of 1996 for the decenial control of the steam generators. The status of the CAPRA project, aimed at demonstrating the feasibility of a fast reactor to burn plutonium at as high a rate as possible and the status of the European Fast Reactor are presented as well as their evolution. Finally the R and D in support of the operation of PHENIX and SUPERPHENIX, in support of the ````knowledge-acquisition```` programme, and CAPRA and EFR programmes is presented, as well as the present status of the stage 2 dismantling of the RAPSODIE experimental fast reactor. (author). 4 refs, figs, 2 tabs.

  19. The transmutation of americium: the Ecrix experiments in Phenix; Transmutation de l'americium: les experiences ecrix dans Phenix

    Energy Technology Data Exchange (ETDEWEB)

    Garnier, J.C.; Schmidt, N. [CEA Cadarache, Dept. d' Etudes des Combustibles (DEC/SESC), 13 - Saint-Paul-lez-Durance (France); Croixmarie, Y.; Ottaviani, J.P. [CEA Cadarache, Dept. d' Etudes des Combustibles (DEC/SPUA), 13 - Saint-Paul-lez-Durance (France); Varaine, F.; Saint Jean, C. de [CEA Cadarache, Dept. d' Etudes des Reacteurs (DER/SPRC), 13 - Saint-Paul-lez-Durance (France)

    1999-07-01

    The first americium transmutation experiment in a specific target in PHENIX will occur with the ECRIX-B and ECRIX-H experiments. Beside material testing, the objective is also to represent a concept of transmutation whose specificity is to enhance the kinetics of transmutation by using a moderated spectrum. The moderator materials will be {sup 11}B{sub 4}C and CaH{sub 2} for ECRIX-B and ECRIXH respectively, the irradiation conditions have been predicted for both the neutronics and thermal. The targets (MgO-AmO{sub X} pellets) are manufactured in the ATALANTE laboratory and the design is performed according to the PHENIX operating conditions. (authors)

  20. Phenix plant - Complementary safety assessment of the Phenix plant (INB 71) in the light of the Fukushima accident

    International Nuclear Information System (INIS)

    2011-01-01

    This CSA (Complementary Safety Assessment) analyses the robustness of the Phenix reactor to extreme situations such as those that led to the Fukushima accident and proposes a series of improvements. The Phenix reactor stands on the Marcoule site of CEA and was stopped definitely in 2009 for electricity production. Robustness is the ability for the facility to withstand events beyond the level for which the facility was designed. Robustness is linked to safety margins but also to the situations leading to a sudden deterioration of the accident sequence (cliff edge effect). Safety is not only a matter of design or of engineered systems, it is also a matter of organization. So issues like crisis organization and work organization via subcontracting are also taken into consideration. This report is divided into 9 main chapters: 1) main features of the Phenix facility, 2) identification of cliff edge risks as well as structures and equipment essential to safety, 3) earthquake risk, 4) flood risk, 5) risks due to other extreme natural disasters, 6) the loss of electrical power supplies and of cooling systems, 7) management of severe accidents, 8) subcontracting policy, 9) synthesis. This study shows that it is necessary to take some measures to reinforce the robustness of the plant concerning flood risks. (A.C.)

  1. PHENIX EXPERIMENT AT RHIC: DECADAL PLAN 2004-2013

    International Nuclear Information System (INIS)

    ZAJC, W.

    2003-01-01

    The PHENIX Collaboration has developed a plan for the detailed investigation of quantum chromodynamics in the next decade. The demonstrated capabilities of the PHENIX experiment to measure rare processes in hadronic, leptonic and photonic channels, in combination with RHIC's unparalleled flexibility as a hadronic collider, provides a physics program of extraordinary breadth and depth. A superlative set of measurements to elucidate the states of both hot and cold nuclear matter, and to measure the spin structure of the proton has been identified. The components of this plan include: (1) Definitive measurements that will establish the nature of the matter created in nucleus+nucleus collisions, that will determine if the description of such matter as a quark-gluon plasma is appropriate, and that will quantify both the equilibrium and non-equilibrium features of the produced medium. (2) Precision measurements of the gluon structure of the proton, and of the spin structure of the gluon and sea-quark distributions of the proton via polarized proton+proton collisions. (3) Determination of the gluon distribution in cold nuclear matter using proton+nucleus collisions. Each of these fundamental fields of investigation will be addressed through a program of correlated measurements in some or all of the following channels: (1) Particle production at high transverse momentum, studied via single particle inclusive measurements of identified charged and neutral hadrons, multi-particle correlations and jet production. (2) Direct photon, photon+jet and virtual photon production. (3) Light and heavy vector mesons. (4) Heavy flavor production. These measurements, together with the established PHENIX abilities to identify hadrons at low transverse momentum, to perform detailed centrality selections, and to monitor polarization and luminosity with high precision create a superb opportunity for performing world-class science with PHENIX for the next decade. A portion of this program is

  2. PHENIX EXPERIMENT AT RHIC: DECADAL PLAN 2004-2013

    Energy Technology Data Exchange (ETDEWEB)

    ZAJC,W.ET. AL.

    2003-11-30

    The PHENIX Collaboration has developed a plan for the detailed investigation of quantum chromodynamics in the next decade. The demonstrated capabilities of the PHENIX experiment to measure rare processes in hadronic, leptonic and photonic channels, in combination with RHIC's unparalleled flexibility as a hadronic collider, provides a physics program of extraordinary breadth and depth. A superlative set of measurements to elucidate the states of both hot and cold nuclear matter, and to measure the spin structure of the proton has been identified. The components of this plan include: (1) Definitive measurements that will establish the nature of the matter created in nucleus+nucleus collisions, that will determine if the description of such matter as a quark-gluon plasma is appropriate, and that will quantify both the equilibrium and non-equilibrium features of the produced medium. (2) Precision measurements of the gluon structure of the proton, and of the spin structure of the gluon and sea-quark distributions of the proton via polarized proton+proton collisions. (3) Determination of the gluon distribution in cold nuclear matter using proton+nucleus collisions. Each of these fundamental fields of investigation will be addressed through a program of correlated measurements in some or all of the following channels: (1) Particle production at high transverse momentum, studied via single particle inclusive measurements of identified charged and neutral hadrons, multi-particle correlations and jet production. (2) Direct photon, photon+jet and virtual photon production. (3) Light and heavy vector mesons. (4) Heavy flavor production. These measurements, together with the established PHENIX abilities to identify hadrons at low transverse momentum, to perform detailed centrality selections, and to monitor polarization and luminosity with high precision create a superb opportunity for performing world-class science with PHENIX for the next decade. A portion of this

  3. Revival.

    International Nuclear Information System (INIS)

    Leclere, J.; Matin, Ph.; Toly, J.A.; Pepe, D.

    1997-01-01

    Because of the promised shutdown and decommissioning of the French Superphenix fast breeder reactor, the French research programs on transmutation will be reoriented towards the smaller Phenix reactor. This issue of 'DRN Actualites' brochure reports on the works carried out by the operator with the help of the Direction of Nuclear Reactors (DRN) of the CEA and Novatome company to satisfy the nuclear safety authorities requirements for the start-up of the Phenix reactor. Three aspects are developed: the 'Service life' project which concerns the non-destructive control of the reactor core and primary circuit, the seismic behaviour of the installation (diagnostic and reinforcement), and the renewal of the secondary circuit and steam generators. (J.S.)

  4. PHENIX central arm tracking detectors

    International Nuclear Information System (INIS)

    Adcox, K.; Ajitanand, N.N.; Alexander, J.; Autrey, D.; Averbeck, R.; Azmoun, B.; Barish, K.N.; Baublis, V.V.; Belkin, R.; Bhaganatula, S.; Biggs, J.C.; Borland, D.; Botelho, S.; Bryan, W.L.; Burward-Hoy, J.; Butsyk, S.A.; Chang, W.C.; Christ, T.; Dietzsch, O.; Drees, A.; Rietz, R. du; El Chenawi, K.; Evseev, V.A.; Fellenstein, J.; Ferdousi, T.; Fraenkel, Z.; Franz, A.; Fung, S.Y.; Gannon, J.; Garpman, S.; Godoi, A.L.; Greene, S.V.; Gustafsson, H.-A.; Harder, J.; Hemmick, T.K.; Heuser, J.M.; Holzmann, W.; Hutter, R.; Issah, M.; Ivanov, V.I.; Jacak, B.V.; Jagadish, U.; Jia, J.; Johnson, S.C.; Kandasamy, A.; Kann, M.R.; Kelley, M.A.; Khanzadeev, A.V.; Khomutnikov, A.; Komkov, B.G.; Kopytine, M.L.; Kotchenda, L.; Kotchetkov, D.; Kozlov, V.S.; Kravtsov, P.A.; Kudin, L.G.; Kuriatkov, V.V.; Lacey, R.; Lauret, J.; Lebedev, A.; Lebedev, V.D.; Li, X.H.; Libby, B.; Liccardi, W.; Machnowski, R.; Mahon, J.; Markushin, D.G.; Matathias, F.; Marx, M.D.; Messer, F.; Miftakhov, N.M.; Milan, J.; Miller, T.E.; Milov, A.; Minuzzo, K.; Mioduszewski, S.; Mitchell, J.T.; Muniruzzamann, M.; Nandi, B.K.; Negrin, J.; Nilsson, P.; Nystrand, J.; O'Brien, E.; O'Connor, P.; Oskarsson, A.; Oesterman, L.; Otterlund, I.; Pancake, C.E.; Pantuev, V.S.; Petersen, R.; Pinkenburg, C.H.; Pisani, R.P.; Purwar, A.K.; Rankowitz, S.; Ravinovich, I.; Riabov, V.G.; Riabov, Yu.G.; Rosati, M.; Rose, A.A.; Roschin, E.V.; Samsonov, V.M.; Sangster, T.C.; Seto, R.; Silvermyr, D.; Sivertz, M.; Smith, M.; Solodov, G.P.; Stenlund, E.; Takagui, E.M.; Tarakanov, V.I.; Tarasenkova, O.P.; Thomas, J.L.; Trofimov, V.A.; Tserruya, I.; Tydesjoe, H.; Velkovska, J.; Velkovsky, M.; Vishnevskii, V.I.; Vorobyov, A.A.; Vznuzdaev, E.A.; Vznuzdaev, M.; Wang, H.Q.; Weimer, T.; Wolniewicz, K.; Wu, J.; Xie, W.; Young, G.R.

    2003-01-01

    The PHENIX tracking system consists of Drift Chambers (DC), Pad Chambers (PC) and the Time Expansion Chamber (TEC). PC1/DC and PC2/TEC/PC3 form the inner and outer tracking units, respectively. These units link the track segments that transverse the RICH and extend to the EMCal. The DC measures charged particle trajectories in the r-phi direction to determine p T of the particles and the invariant mass of particle pairs. The PCs perform 3D spatial point measurements for pattern recognition and longitudinal momentum reconstruction and provide spatial resolution of a few mm in both r-phi and z. The TEC tracks particles passing through the region between the RICH and the EMCal. The design and operational parameters of the detectors are presented and running experience during the first year of data taking with PHENIX is discussed. The observed spatial and momentum resolution is given which imposes a limitation on the identification and characterization of charged particles in various momentum ranges

  5. Overview of the fast reactors fuels program

    International Nuclear Information System (INIS)

    Evans, E.A.; Cox, C.M.; Hayward, B.R.; Rice, L.H.; Yoshikawa, H.H.

    1980-04-01

    Each nation involved in LMFBR development has its unique energy strategies which consider energy growth projections, uranium resources, capital costs, and plant operational requirements. Common to all of these strategies is a history of fast reactor experience which dates back to the days of the Manhatten Project and includes the CLEMENTINE Reactor, which generated a few watts, LAMPRE, EBR-I, EBR-II, FERMI, SEFOR, FFTF, BR-1, -2, -5, -10, BOR-60, BN-350, BN-600, JOYO, RAPSODIE, Phenix, KNK-II, DFR, and PFR. Fast reactors under design or construction include PEC, CRBR, SuperPhenix, SNR-300, MONJU, and Madras (India). The parallel fuels and materials evolution has fully supported this reactor development. It has involved cermets, molten plutonium alloy, plutonium oxide, uranium metal or alloy, uranium oxide, and mixed uranium-plutonium oxides and carbides

  6. The experience of five years operation of Phenix

    International Nuclear Information System (INIS)

    Conte, F.; Lacroix, A.

    1980-01-01

    Two long periods of exceptional operation have satisfied the hopes of the designers and all parameters, power, efficiency, load factor, fuel behaviour, were better than was expected. The experience resulting from the only major incident provided a series of complementary data. Modern technology has need of sanction by experiment. The Phenix type reactor is a tool which is convenient to operate and to maintain. The two aspects of the demonstration, correct operation and ease of maintenance, take a concrete form in the harmlessness of Phenix on men and on the environment. There is no irradiation and few releases. (orig./DG)

  7. Production and performance of the silicon sensor and readout electronics for the PHENIX FVTX tracker

    International Nuclear Information System (INIS)

    Kapustinsky, Jon Steven

    2009-01-01

    The Forward Silicon Vertex Tracker (FVTX) upgrade for the PHENIX detector at RHIC will extend the vertex capability of the central PHENIX Silicon Vertex Tracker (VTX). The FVTX is designed with adequate spatial resolution to separate decay muons coming from the relatively long-lived heavy quark mesons (Charm and Beauty), from prompt particles and the longer-lived pion and kaon decays that originate at the primary collision vertex. These heavy quarks can be used to probe the high density medium that is formed in Au+Au collisions at RHIC. The FVTX is designed as two endcaps. Each endcap is comprised of four silicon disks covering opening angles from 10 to 35 degrees to match the existing muon arm acceptance. Each disk consists of p-on-n, silicon wedges, with ac-coupled mini-strips on 75 (micro)m radial pitch and proj ective length in the phi direction that increases with radius. A custom front-end chip, the FPHX, has been designed for the FVTX. The chip combines fast trigger capability with data push architecture in a low power design.

  8. Shielding design method for LMFBR validation on the Phenix factor

    International Nuclear Information System (INIS)

    Cabrillat, J.C.; Crouzet, J.; Misrakis, J.; Salvatores, M.; Rado, V.; Palmiotti, G.

    1983-05-01

    Shielding design methods, developed at CEA for shielding calculations find a global validation by the means of Phenix power reactor (250 MWe) measurements. Particularly, the secondary sodium activation of pool type LMFBR such as Super Phenix (1200 MWe) which is subject to strict safety limitation is well calculated by the adapted scheme, i.e. a two dimension transport calculation of shielding coupled to a Monte-Carlo calculation of secondary sodium activation

  9. Pu utilization in fast-breeder and in light-water reactors in Italy

    International Nuclear Information System (INIS)

    Mangiagalli, D.; Cicognani, F.; Pistella, F.; Testa, G.; Villani, A.; Ariemma, A.; Castelli, G.F.; Linari, A.; Paoletti Gualandi, M.; Musso, B.

    1977-01-01

    The paper illustrates the most important activities carried out in Italy for the development of fast breeder reactors and its fuel as well as for plutonium recycle in light water reactors. The Italian strategy is based, on one hand, on the short-term commercialization of fast breeder reactors, and on the other, on the adoption of the technology of the Phenix prototype whose further development will be ensured by the joint Italian and French efforts as insured by the important agreements signed by CNEN, NIRA (Nucleare Italiana Reattori Avanzati) and Italian manufacturing industries with CEA and the main French industries. The paper also includes the main results of the ENEL Demonstration Program on Pu prototypes introduced in the Garigliano BWR in 1968 and 1970, and of the destructive and non-destructive analyses on said fuel, as well as of the analyses carried out by CNEN on prototypical fuel fabricated by CNEN and irradiated in various reactors. Furthermore, the paper deals with design and licensing aspects of the 46 Pu-island assembly reload introduced in the Garigliano reactors in 1975 and of a batch of 8 all Pu assemblies loaded in the Trino Vercellese PWR in 1976. Subsequently, the experimental activities planned for the near future both on high burn-up prototypes and on industrial fuel after one cycle of operation are examined [fr

  10. Sodium tests on an integrated purification prototype for a sodium-cooled fast breeder reactor

    International Nuclear Information System (INIS)

    Abramson, R.

    1984-04-01

    This paper describes sodium tests performed on the integrated primary sodium purification prototype of the Creys Malville Super Phenix 1 fast breeder reactor. These tests comprised: - hydrostatic test, - thermal tests, - handling tests. They enabled a number of new technological arrangements to be qualified and provided the necessary information for the design and construction of the Super Phenix 1 purification units

  11. sPHENIX: The next generation heavy ion detector at RHIC

    Science.gov (United States)

    Campbell, Sarah; sPHENIX Collaboration

    2017-04-01

    sPHENIX is a new collaboration and future detector project at Brookhaven National Laboratory’s Relativistic Heavy Ion Collider (RHIC). It seeks to answer fundamental questions on the nature of the quark gluon plasma (QGP), including its coupling strength and temperature dependence, by using a suite of precision jet and upsilon measurements that probe different length scales of the QGP. This is possible with a full acceptance, |η| superconducting magnet. With the increased luminosity afforded by accelerator upgrades, sPHENIX is going to perform high statistics measurements extending the kinematic reach at RHIC to overlap the LHC’s. This overlap is going to facilitate a better understanding of the role of temperature, density and parton virtuality in QGP dynamics and, specifically, jet quenching. This paper focuses on key future measurements and the current state of the sPHENIX project.

  12. PHENIX Muon Arms

    International Nuclear Information System (INIS)

    Akikawa, H.; Al-Jamel, A.; Archuleta, J.B.; Archuleta, J.R.; Armendariz, R.; Armijo, V.; Awes, T.C.; Baldisseri, A.; Barker, A.B.; Barnes, P.D.; Bassalleck, B.; Batsouli, S.; Behrendt, J.; Bellaiche, F.G.; Bland, A.W.; Bobrek, M.; Boissevain, J.G.; Borel, H.; Brooks, M.L.; Brown, A.W.; Brown, D.S.; Bruner, N.; Cafferty, M.M.; Carey, T.A.; Chai, J.-S.; Chavez, L.L.; Chollet, S.; Choudhury, R.K.; Chung, M.S.; Cianciolo, V.; Clark, D.J.; Cobigo, Y.; Dabrowski, C.M.; Debraine, A.; DeMoss, J.; Dinesh, B.V.; Drachenberg, J.L.; Drapier, O.; Echave, M.A.; Efremenko, Y.V.; En'yo, H.; Fields, D.E.; Fleuret, F.; Fried, J.; Fujisawa, E.; Funahashi, H.; Gadrat, S.; Gastaldi, F.; Gee, T.F.; Glenn, A.; Gogiberidze, G.; Gonin, M.; Gosset, J.; Goto, Y.; Granier de Cassagnac, R.; Hance, R.H.; Hart, G.W.; Hayashi, N.; Held, S.; Hicks, J.S.; Hill, J.C.; Hoade, R.; Hong, B.; Hoover, A.; Horaguchi, T.; Hunter, C.T.; Hurst, D.E.; Ichihara, T.; Imai, K.; Isenhower, L.D.L. Davis; Isenhower, L.D.L. Donald; Ishihara, M.; Jang, W.Y.; Johnson, J.; Jouan, D.; Kamihara, N.; Kamyshkov, Y.; Kang, J.H.; Kapoor, S.S.; Kim, D.J.; Kim, D.-W.; Kim, G.-B.; Kinnison, W.W.; Klinksiek, S.; Kluberg, L.; Kobayashi, H.; Koehler, D.; Kotchenda, L.; Kuberg, C.H.; Kurita, K.; Kweon, M.J.; Kwon, Y.; Kyle, G.S.; LaBounty, J.J.; Lajoie, J.G.; Lee, D.M.; Lee, S.; Leitch, M.J.; Li, Z.; Liu, M.X.; Liu, X.; Liu, Y.; Lockner, E.; Lopez, J.D.; Mao, Y.; Martinez, X.B.; McCain, M.C.; McGaughey, P.L.; Mioduszewski, S.; Mischke, R.E.; Mohanty, A.K.; Montoya, B.C.; Moss, J.M.; Murata, J.; Murray, M.M.; Nagle, J.L.; Nakada, Y.; Newby, J.; Obenshain, F.; Palounek, A.P.T.; Papavassiliou, V.; Pate, S.F.; Plasil, F.; Pope, K.; Qualls, J.M.; Rao, G.; Read, K.F.; Robinson, S.H.; Roche, G.; Romana, A.; Rosnet, P.; Roth, R.; Saito, N.; Sakuma, T.; Sandhoff, W.F.; Sanfratello, L.; Sato, H.D.; Savino, R.; Sekimoto, M.; Shaw, M.R.; Shibata, T.-A.; Sim, K.S.; Skank, H.D.; Smith, D.E.; Smith, G.D.; Sondheim, W.E.; Sorensen, S.; Staley, F.; Stankus, P.W.; Steffens, S.; Stein, E.M.; Stepanov, M.; Stokes, W.; Sugioka, M.; Sun, Z.; Taketani, A.; Taniguchi, E.; Tepe, J.D.; Thornton, G.W.; Tian, W.; Tojo, J.; Torii, H.; Towell, R.S.; Tradeski, J.; Vassent, M.; Velissaris, C.; Villatte, L.; Wan, Y.; Watanabe, Y.; Watkins, L.C.; Whitus, B.R.; Williams, C.; Willis, P.S.; Wong-Swanson, B.G.; Yang, Y.; Yoneyama, S.; Young, G.R.; Zhou, S.

    2003-01-01

    The PHENIX Muon Arms detect muons at rapidities of |y|=(1.2-2.4) with full azimuthal acceptance. Each muon arm must track and identify muons and provide good rejection of pions and kaons (∼10 -3 ). In order to accomplish this we employ a radial field magnetic spectrometer with precision tracking (Muon Tracker) followed by a stack of absorber/low resolution tracking layers (Muon Identifier). The design, construction, testing and expected run parameters of both the muon tracker and the muon identifier are described

  13. PHENIX Muon Arms

    Energy Technology Data Exchange (ETDEWEB)

    Akikawa, H.; Al-Jamel, A.; Archuleta, J.B.; Archuleta, J.R.; Armendariz, R.; Armijo, V.; Awes, T.C.; Baldisseri, A.; Barker, A.B.; Barnes, P.D.; Bassalleck, B.; Batsouli, S.; Behrendt, J.; Bellaiche, F.G.; Bland, A.W.; Bobrek, M.; Boissevain, J.G.; Borel, H.; Brooks, M.L.; Brown, A.W.; Brown, D.S.; Bruner, N.; Cafferty, M.M.; Carey, T.A.; Chai, J.-S.; Chavez, L.L.; Chollet, S.; Choudhury, R.K.; Chung, M.S.; Cianciolo, V.; Clark, D.J.; Cobigo, Y.; Dabrowski, C.M.; Debraine, A.; DeMoss, J.; Dinesh, B.V.; Drachenberg, J.L.; Drapier, O.; Echave, M.A.; Efremenko, Y.V.; En' yo, H.; Fields, D.E.; Fleuret, F.; Fried, J.; Fujisawa, E.; Funahashi, H.; Gadrat, S.; Gastaldi, F.; Gee, T.F.; Glenn, A.; Gogiberidze, G.; Gonin, M.; Gosset, J.; Goto, Y.; Granier de Cassagnac, R.; Hance, R.H.; Hart, G.W.; Hayashi, N.; Held, S.; Hicks, J.S.; Hill, J.C.; Hoade, R.; Hong, B.; Hoover, A.; Horaguchi, T.; Hunter, C.T.; Hurst, D.E.; Ichihara, T.; Imai, K.; Isenhower, L.D.L. Davis; Isenhower, L.D.L. Donald; Ishihara, M.; Jang, W.Y.; Johnson, J.; Jouan, D.; Kamihara, N.; Kamyshkov, Y.; Kang, J.H.; Kapoor, S.S.; Kim, D.J.; Kim, D.-W.; Kim, G.-B.; Kinnison, W.W.; Klinksiek, S.; Kluberg, L.; Kobayashi, H.; Koehler, D.; Kotchenda, L.; Kuberg, C.H.; Kurita, K.; Kweon, M.J.; Kwon, Y.; Kyle, G.S.; LaBounty, J.J.; Lajoie, J.G.; Lee, D.M.; Lee, S.; Leitch, M.J.; Li, Z.; Liu, M.X.; Liu, X.; Liu, Y.; Lockner, E.; Lopez, J.D.; Mao, Y.; Martinez, X.B.; McCain, M.C.; McGaughey, P.L.; Mioduszewski, S.; Mischke, R.E.; Mohanty, A.K.; Montoya, B.C.; Moss, J.M.; Murata, J.; Murray, M.M.; Nagle, J.L.; Nakada, Y.; Newby, J.; Obenshain, F.; Palounek, A.P.T.; Papavassiliou, V.; Pate, S.F.; Plasil, F.; Pope, K.; Qualls, J.M.; Rao, G.; Read, K.F. E-mail: readkf@ornl.gov; Robinson, S.H.; Roche, G.; Romana, A.; Rosnet, P.; Roth, R.; Saito, N.; Sakuma, T.; Sandhoff, W.F.; Sanfratello, L.; Sato, H.D.; Savino, R.; Sekimoto, M.; Shaw, M.R.; Shibata, T.-A.; Sim, K.S.; Skank, H.D.; Smith, D.E.; Smith, G.D. [and others

    2003-03-01

    The PHENIX Muon Arms detect muons at rapidities of |y|=(1.2-2.4) with full azimuthal acceptance. Each muon arm must track and identify muons and provide good rejection of pions and kaons ({approx}10{sup -3}). In order to accomplish this we employ a radial field magnetic spectrometer with precision tracking (Muon Tracker) followed by a stack of absorber/low resolution tracking layers (Muon Identifier). The design, construction, testing and expected run parameters of both the muon tracker and the muon identifier are described.

  14. Trigger circuits for the PHENIX electromagnetic calorimeter

    International Nuclear Information System (INIS)

    Frank, S.S.; Britton, C.L. Jr.; Winterberg, A.L.; Young, G.R.

    1997-11-01

    Monolithic and discrete circuits have been developed to provide trigger signals for the PHENIX electromagnetic calorimeter detector. These trigger circuits are deadtimeless and create overlapping 4 by 4 energy sums, a cosmic muon trigger, and a 144 channel energy sum. The front end electronics of the PHENIX system sample the energy and timing channels at each bunch crossing (BC) but it is not known immediately if this data is of interest. The information from the trigger circuits is used to determine if the data collected is of interest and should be digitized and stored or discarded. This paper presents details of the design, issues affecting circuit performance, characterization of prototypes fabricated in 1.2 microm Orbit CMOS, and integration of the circuits into the EMCal electronics system

  15. Surveillance of a nuclear reactor by pattern recognition analysis of the neutronic noise. Experience on Phenix LMFBR

    International Nuclear Information System (INIS)

    Le Guillou, G.; Bernardin, B.

    1980-05-01

    The purpose of this paper is to present some results of pattern recognition methods applied to the problem of supervising the behaviour of a nuclear reactor, especially the sodium cooled fast breeder Phenix. The problem to solve can be divided into two parts: first, from a set of data about the behaviour of the reactor, we have to find consistent classes of functionning. These classes must be interpreted by physical considerations; then, we have to elaborate a simple classification algorithm, which can be used in-line, to improve safety systems of fast breeder reactors, by giving helpful information for decision making. The neutronic noise has been chosen for our study

  16. Identification and adoptive multivariable control method. Application to fast breeder nuclear reactors

    International Nuclear Information System (INIS)

    Dang Van Mien, H.; Irving, E.; Rousseau, I.

    1982-01-01

    Motivated by the limitations inherent in the standard approach, a new model reference multivariable adaptive control method is described. This latter control method utilizes as a design tool a simple vector difference equation of the controlled system. The adaptive control method is of the series-parallel direct reference model type and the adjustment algorithm is the standard least squares estimation technics with hyperstability conditions, controlled convergence speed forgetting, regularization and threshold operations. Numerical results are presented which illustrate the interest of the latter approach. The precise problem which has been tackled is the control of the steam generator of the second fast breeder French nuclear reactor called Super-Phenix. After a short description of the plant and its responses at different loads, the principles and the performances of the standard technique control scheme which has been adopted are discussed [fr

  17. The control system adopted for Super-Phenix. Reasons for choice and evaluation of performance

    International Nuclear Information System (INIS)

    Decuyper, J.; Skull, G.; Hery, M.; Hennebicq, J.P.

    1978-01-01

    The paper reviews all the research done in working out the control system for the fast-neutron Super-Phenix power station, which is now under construction at Creys-Malville, France. The purpose of the system is to provide a balance between the power produced by the reactor and that taken by the electricity-generating plant. After an introductory section on the structure of the power station and the operating conditions imposed, the following main stages in design work are described: development of the system simulation model and corrobaration on the basis of test results; specification of possible control system layouts (i.e. the various possible connections between regulating variables and regulated variables), optimization of control coefficients of each layout, comparison of performance and choice of layout; detailed study of the layout chosen. Special reference is made to the following typical aspects of Super-Phenix operating technology: response of the power station to primary frequency control; stability of steam generators operating in parallel; establishment of the sodium temperature value. The final part is a summary of the research carried out and a description of the performance of the computer codes. (author)

  18. Overview of the fast reactors fuels program. [LMFBR

    Energy Technology Data Exchange (ETDEWEB)

    Evans, E.A.; Cox, C.M.; Hayward, B.R.; Rice, L.H.; Yoshikawa, H.H.

    1980-04-01

    Each nation involved in LMFBR development has its unique energy strategies which consider energy growth projections, uranium resources, capital costs, and plant operational requirements. Common to all of these strategies is a history of fast reactor experience which dates back to the days of the Manhatten Project and includes the CLEMENTINE Reactor, which generated a few watts, LAMPRE, EBR-I, EBR-II, FERMI, SEFOR, FFTF, BR-1, -2, -5, -10, BOR-60, BN-350, BN-600, JOYO, RAPSODIE, Phenix, KNK-II, DFR, and PFR. Fast reactors under design or construction include PEC, CRBR, SuperPhenix, SNR-300, MONJU, and Madras (India). The parallel fuels and materials evolution has fully supported this reactor development. It has involved cermets, molten plutonium alloy, plutonium oxide, uranium metal or alloy, uranium oxide, and mixed uranium-plutonium oxides and carbides.

  19. Fast reactor development programme in France during 1995

    International Nuclear Information System (INIS)

    Le Rigoleur, C.

    1996-01-01

    In 1995, the total amount of electricity produced in France was 471 TWh, out of which 358.2 TWh (76 %) were produced by nuclear power plants, 36.9 TWh (7.8 %) by conventional thermal plants, and 75.5 TWh (16 %) by hydraulic plants. The net electrical power consumption was 368.7 TWh. At the end of 1995, 'Electricite de France' had 54 PWR units in operation. The availability factor for these units was maintained at 81%. 1995 was marked by a decrease of unexpected shutdowns (1.8% in 1995 instead of 2.2% in 1994), a new reduction in programmed shutdown periods, and a good safety level was maintained. In the field of Fast Reactors, the main events of 1995 were the following. At the end of December 1994, the PHENIX reactor was authorized to perform its 49th cycle at 350 MW th (143 MWe). This 49th cycle was completed without any significant problems on April 7, 1995. During the remainder of the year, the reactor had been shut down in order to carry out several tasks within the scope of the ten-year extension of the PHENIX reactor's lifetime. Concerning the CREYS-MALVILLE plant (SUPER-PHENIX) the first part of the year was devoted to repairing argon leak of one of the IHX. Authorization to restart the reactor was given on August 22. The end of the year was beset by a number of minor incidents. The reactor was restarted at the end of 1995 and reactor power was increased by successive steps (30% Pn (Nominal Power) up to February 6 1996; followed by 50 %...). The 'Decret d'Autorisation de Creation' stipulates that because of its prototype character, SUPER PHENIX will have to be operated under conditions explicitly giving priority to safety and knowledge acquisition, with an objective of research and demonstration. In this context, the so-called 'knowledge acquisition' programme designed to prove the capacity of a large FBR to produce electricity on an industrial scale, to test the consumption of plutonium and minor actinides in a large fast reactor, as well as to provide

  20. Overview of the system alone and system/CFD coupled calculations of the PHENIX Natural Circulation Test within the THINS project

    Energy Technology Data Exchange (ETDEWEB)

    Pialla, David, E-mail: david.pialla@cea.fr [Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), DEN/DM2S/STMF, 17 rue des martyrs, 38054 Grenoble Cedex 9 (France); Tenchine, Denis [Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), DEN/DM2S/STMF, 17 rue des martyrs, 38054 Grenoble Cedex 9 (France); Li, Simon [Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), DEN/DM2S/STMF, 91191 Gif-sur-Yvette Cedex (France); Gauthe, Paul; Vasile, Alfredo [Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), DEN/DER/SESI, 13108 Saint Paul Lez Durance Cedex (France); Baviere, Roland; Tauveron, Nicolas; Perdu, Fabien [Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), DEN/DM2S/STMF, 17 rue des martyrs, 38054 Grenoble Cedex 9 (France); Maas, Ludovic; Cocheme, François [Institut de Radioprotection et de Sûreté Nucléaire (IRSN), PSN/SEMIA/BAST, B.P. 17, 92262 Fontenay-aux-Roses Cedex (France); Huber, Klaus; Cheng, Xu [Karlsruhe Institute of Technology (KIT), Institute of Fusion and Reactor Technology (IFRT), Kaiserstraße 12, Building 07.08, 76131 Karlsruhe (Germany)

    2015-08-15

    Highlights: • The PHENIX natural convection test performed during the end of life tests program. • The calculation with system codes and theirs limits. • The calculation with coupling CFD and system code, which allows better prediction. • The tasks of code validation have been done in the frame of the THINS project. - Abstract: The PHENIX sodium cooled fast reactor started operation in 1973 and was shut down in 2009. Before decommissioning, an ultimate test program was designed and performed to provide valuable data for the development of future sodium cooled fast reactors, as the so-called Astrid prototype in France. Among these ultimate tests, a thermal-hydraulic Natural Convection Test (NCT) was set-up in June 2009. Starting from a reduced power state of 120 MWt, the NCT consists of a loss of the heat sink combined with a reactor scram and a primary pumps trip leading to stabilized natural circulation in the primary sodium system. The thermal-hydraulics innovative system project (THINS project), sponsored by the European Community in the frame of the 7th FP has selected this transient for validation of both stand-alone system code simulations and coupled simulations using system and CFD codes. Participants from three organizations (CEA, IRSN and KIT) have addressed this transient using different system codes (CATHARE, DYN2B and ATHLET) and CFD codes (TRIO-U and OPEN FOAM). The present paper depicts the different modeling approaches, methodologies and compares the numerical results with the available experimental data. Finally, the main lessons learned from the work performed within the THINS project on the PHENIX NCT with respect to code development and validation are summarized.

  1. Production and performance of the silicon sensor and custom readout electronics for the PHENIX FVTX tracker

    International Nuclear Information System (INIS)

    Kapustinsky, Jon S.

    2010-01-01

    The Forward Silicon Vertex Tracker (FVTX) upgrade for the PHENIX detector at RHIC will extend the vertex capability of the central PHENIX Silicon Vertex Tracker (VTX). The FVTX is designed with adequate spatial resolution to separate decay muons coming from the relatively long-lived heavy quark mesons (Charm and Beauty), from prompt particles and the longer-lived pion and kaon decays that originate at the primary collision vertex. These heavy quarks can be used to probe the high-density medium that is formed in Au+Au collisions at RHIC. The FVTX is designed as two endcaps. Each endcap comprises four silicon disks covering opening angles from 10 o to 35 o to match the existing muon arm acceptance. Each disk consists of p-on-n, silicon wedges, with ac-coupled mini-strips on 75 μm radial pitch and projective length in the phi direction that increases with radius. A custom front-end chip, the FPHX, has been designed for the FVTX. The chip combines fast trigger capability with data push architecture in a low-power design.

  2. Production and performance of the silicon sensor and custom readout electronics for the PHENIX FVTX tracker

    Energy Technology Data Exchange (ETDEWEB)

    Kapustinsky, Jon S., E-mail: jonk@lanl.go [Los Alamos National Laboratory, Mailstop H846, PO Box 1663, Los Alamos, 87545 New Mexico (United States)

    2010-05-21

    The Forward Silicon Vertex Tracker (FVTX) upgrade for the PHENIX detector at RHIC will extend the vertex capability of the central PHENIX Silicon Vertex Tracker (VTX). The FVTX is designed with adequate spatial resolution to separate decay muons coming from the relatively long-lived heavy quark mesons (Charm and Beauty), from prompt particles and the longer-lived pion and kaon decays that originate at the primary collision vertex. These heavy quarks can be used to probe the high-density medium that is formed in Au+Au collisions at RHIC. The FVTX is designed as two endcaps. Each endcap comprises four silicon disks covering opening angles from 10{sup o} to 35{sup o} to match the existing muon arm acceptance. Each disk consists of p-on-n, silicon wedges, with ac-coupled mini-strips on 75 {mu}m radial pitch and projective length in the phi direction that increases with radius. A custom front-end chip, the FPHX, has been designed for the FVTX. The chip combines fast trigger capability with data push architecture in a low-power design.

  3. The Creys Malville FBR Super Phenix steam generators

    International Nuclear Information System (INIS)

    Baque, P.; Zuber, T.; Saur, J.M.; Cambillard, E.

    1980-08-01

    After briefly recalling the French experience on sodium steam generators, the authors describe the design concepts of the Superphenix units and give their main characteristics. A short summary of the realized R and D program precedes the description of the four 750-MWt steam generators, the fabrication of which is in progress by Creusot-Loire at Chalon sur Saone (France). The studies started for the next French fast breeder reactors and their steam generators are mentioned

  4. Front-end readout system for PHENIX RICH

    International Nuclear Information System (INIS)

    Tanaka, Y.; Hara, H.; Ebisu, K.; Hibino, M.; Kametani, S.; Kikuchi, J.; Wintenberg, A.L.; Walker, J.W.; Franck, S.; Moscone, C.; Jones, J.P.; Young, G.R.; Matsumoto, T.; Sakaguchi, T.; Oyama, K.; Hamagaki, H.

    2000-01-01

    A front-end readout system with a custom backplane and custom circuit modules has been developed for the RICH subsystem of the PHENIX experiment. The design specifications and test results of the backplane and the modules are presented in this paper. In the module design, flexibility for modification is maximized through the use of Complex Programmable Logic Devices. In the backplane design, a source-synchronous bus architecture is adopted for the data and control bus. The transfer speed of the backplane has reached 640 Mbyte/s with a 128-bit data bus. Total transaction time is estimated to be less than 30 μs per event when this system is used in the experiment. This result indicates that the performance satisfies the data-rate requirement of the PHENIX experiment

  5. Implementation of PHENIX trigger algorithms on massively parallel computers

    International Nuclear Information System (INIS)

    Petridis, A.N.; Wohn, F.K.

    1995-01-01

    The event selection requirements of contemporary high energy and nuclear physics experiments are met by the introduction of on-line trigger algorithms which identify potentially interesting events and reduce the data acquisition rate to levels that are manageable by the electronics. Such algorithms being parallel in nature can be simulated off-line using massively parallel computers. The PHENIX experiment intends to investigate the possible existence of a new phase of matter called the quark gluon plasma which has been theorized to have existed in very early stages of the evolution of the universe by studying collisions of heavy nuclei at ultra-relativistic energies. Such interactions can also reveal important information regarding the structure of the nucleus and mandate a thorough investigation of the simpler proton-nucleus collisions at the same energies. The complexity of PHENIX events and the need to analyze and also simulate them at rates similar to the data collection ones imposes enormous computation demands. This work is a first effort to implement PHENIX trigger algorithms on parallel computers and to study the feasibility of using such machines to run the complex programs necessary for the simulation of the PHENIX detector response. Fine and coarse grain approaches have been studied and evaluated. Depending on the application the performance of a massively parallel computer can be much better or much worse than that of a serial workstation. A comparison between single instruction and multiple instruction computers is also made and possible applications of the single instruction machines to high energy and nuclear physics experiments are outlined. copyright 1995 American Institute of Physics

  6. Progress of the OODB study for PHENIX

    International Nuclear Information System (INIS)

    Ye Yanlin; Ying Jun; Xu Chuncheng; Chen Tao

    1997-01-01

    The background for developing Object-Oriented software technique in high-energy and nuclear physics has been outlined. The need for Object-oriented Database for PHENIX was analyzed. A prototype for PEP production control database is introduced

  7. sPHENIX: The next generation heavy ion detector at RHIC

    International Nuclear Information System (INIS)

    Campbell, Sarah

    2017-01-01

    sPHENIX is a new collaboration and future detector project at Brookhaven National Laboratory’s Relativistic Heavy Ion Collider (RHIC). It seeks to answer fundamental questions on the nature of the quark gluon plasma (QGP), including its coupling strength and temperature dependence, by using a suite of precision jet and upsilon measurements that probe different length scales of the QGP. This is possible with a full acceptance, | η | < 1 and 0-2 π in φ , electromagentic and hadronic calorimeters and precision tracking enabled by a 1.5 T superconducting magnet. With the increased luminosity afforded by accelerator upgrades, sPHENIX is going to perform high statistics measurements extending the kinematic reach at RHIC to overlap the LHC’s. This overlap is going to facilitate a better understanding of the role of temperature, density and parton virtuality in QGP dynamics and, specifically, jet quenching. This paper focuses on key future measurements and the current state of the sPHENIX project. (paper)

  8. Performance of the steam generators of Phenix in steady-state operation - comparison with predicted values; Performances des generateurs de vapeur de Phenix en regime permanent: Comparison avec les previsions

    Energy Technology Data Exchange (ETDEWEB)

    Robin, M G; Duchatelle, L; De Nucheze, L

    1975-07-01

    Theoretical and experimental performances in steady state conditions of the prototype modules and the commercial unit of the Phenix Steam Generator were compared. It is shown that, as early as 1969, our computer code allowed us a fair prediction of the required heat transfer area, and of the full load performance of the Phenix Steam Generator. (author)

  9. Highlights from PHENIX transverse spin program at RHIC

    International Nuclear Information System (INIS)

    Liu, M.

    2013-01-01

    In recent years, there has been exciting development in both experimental and theoretical studies of transverse spin phenomena in high energy polarized p+p and polarized DIS collisions. In the p+p frontier, the polarized p+p collider at RHIC provides a unique opportunity to investigate the novel physics that causes the large spin effects seen in the transversely polarized p+p collisions over the past 30 years, particularly in the forward rapidity. Since the beginning, PHENIX has been conducting a very active transverse spin physics program to study Sivers, Collins and other novel spin effects at RHIC, including measurements of transverse single spin asymmetry (TSSA) in light and heavy quark productions, leading neutron TSSA in the very forward rapidity, and di-hadron (and 'jet') spin correlations in a wide kinematics range, just to name a few. In 2012, PHENIX collected transversely polarized 200 GeV p+p data with a record high luminosity of 9.24 pb −1 , with an average beam polarization of 58%. In this talk, I highlight the recent results from the PHENIX experiment, and also briefly discuss the near-term prospects of new transverse spin measurements only possible with the latest (forward) silicon vertex detectors, (F)VTX, and the upcoming forward MPC-EX upgrade detectors.

  10. Conception and fabrication of innovative Am-Based targets: the ca mix/Cochix experiment

    International Nuclear Information System (INIS)

    Schmidt, N.; Croixmarie, Y.; Abonneau, E.; Ottaviani, J.P.; Donnet, L.; Desmouliere, F.; Konings, R.J.M.; Fernandez, A.

    2003-01-01

    A large experimental programme has been planned to be carried out in the French PHENIX reactor. The purpose is to evaluate the technical feasibility of minor actinide transmutation in fast reactors. Two major series of experiments have been designed for the heterogeneous transmutation mode. The first one, the MATINA (Matrices for Incineration of Actinides) series, aims at testing both different inert matrices in a fast flux and different concepts. The study is generic and focuses on the material behaviour under representative irradiation conditions. Targets are free of minor actinides to make the fabrication and design steps easier and faster. The second one, ECRIX, CAMIX (Compounds of Americium in PHENIX) and COCHIX (Concept Optimized microstructure in PHENIX), is a further step in the demonstration phase of the ''once-through'' transmutation and deals with Am-bearing targets irradiated in a fast neutron spectrum ''locally'' moderated. The moderator materials tested will be calcium hydride CaH 2-x (cases of ECRIX-H, CAMIX and COCHIX) and boron carbide 11 B 4 C (case of ECRIX-B) in order to accelerate the process of transmutation significantly. (author)

  11. Vibrations measurement in fast and PWR reactor study

    International Nuclear Information System (INIS)

    Tigeot, Y.; Epstein, A.; Hareux, F.

    1975-01-01

    In the past severe damages have occured in several nuclear reactors, by structural vibrations induced by the primary cooling flow. To avoid this kind of troubles, the SEMT makes studies for two different types of reactors. For the light pressurized water reactors, some tests have been made on the SAFRAN test loop which is a three loop 1/8 scale internal model of a 900 MWe reactor. This study is actually undertaken jointly with Framatome. Elsewhere, measurements have been made on the Phenix fast breeder sodium reactor, and studies are planned for the Super Phenix reactor [fr

  12. Super Phenix. Monitoring of structures subject to irradiation. Neutron dosimetry measurement and calculation program

    International Nuclear Information System (INIS)

    Cabrillat, J.C.; Arnaud, G.; Calamand, D.; Manent, G.; Tavassoli, A.A.

    1984-09-01

    For the Super Phenix reactor, the evolution, versus the irradiation of the mechanical properties of the core diagrid steel is the object of studies and is particularly monitored. The specimens irradiated, now in PHENIX and will be later irradiated in SUPER PHENIX as soon as the first operating cycles. An important dosimetry program coupling calculation and measurement, is parallely carried out. This paper presents the reasons, the definition of the structure, of the development and of materials used in this program of dosimetry, as also the first results of a calculation-measurement comparison [fr

  13. Sodium fast reactor power monitoring using {sup 20}F tagging agent

    Energy Technology Data Exchange (ETDEWEB)

    Coulon, R.; Normand, S. [CEA, LIST, Laboratoire Capteurs et Architectures Electroniques, Centre de Saclay, 91191 Gif sur Yvette Cedex (France); Ban, G. [ENSICAEN, F-14050 Caen (France); Dumarcher, V.; Brau, H. P.; Barbot, L.; Domenech, T.; Kondrasovs, V.; Corre, G.; Frelin, A. M.; Montagu, T.; Dautremer, T.; Barat, E.

    2009-07-01

    This work deals with the use of gamma spectrometry to monitor the fourth generation sodium fast reactor (SFR) power. Simulation part has shown that power monitoring in short response time and with high accuracy is possible measuring delayed gamma emitters produced in the liquid sodium. An experimental test is under preparation at French SFR Phenix experimental reactor to validate simulation studies. Physical calculations have been done to correlate gamma activity to the released thermal power. Gamma emitter production rate in the reactor core was calculated with technical and nuclear data as sodium velocity, atomic densities, neutron spectra and incident neutron cross-sections of fission reactions, and also sodium activation reactions producing gamma emitters. Then, a thermal hydraulic transfer function was used for taking into account primary sodium flow in our calculations. Gamma spectra were then determined by Monte-Carlo simulations. The experiment will be set during the reactor 'ultimate testing'. The Delayed Neutron Detection (DND) system cell has been chosen as the best available primary sodium sample for gamma power monitoring on Phenix reactor due to short sodium transit time from reactor core to measurement sample and homogenized sampling in the reactor hot pool. The main gamma spectrometer is composed of a coaxial high purity germanium diode (HPGe) coupled with a transistor reset preamplifier. The signal is then processed by a digital signal processing system (called Adonis) which always gives optimum answer even for high count rate and various time activity measurements. For power monitoring problematic, use of a short decay period gamma emitter as the {sup 20}F will allow to obtain a very fast response system without cumulative and flow distortion effects. These works introduce advantages and performances of this new power monitoring system for future SFR. (authors)

  14. The transmutation of americium: the Ecrix experiments in Phenix

    International Nuclear Information System (INIS)

    Garnier, J.C.; Schmidt, N.; Croixmarie, Y.; Ottaviani, J.P.; Varaine, F.; Saint Jean, C. de

    1999-01-01

    The first americium transmutation experiment in a specific target in PHENIX will occur with the ECRIX-B and ECRIX-H experiments. Beside material testing, the objective is also to represent a concept of transmutation whose specificity is to enhance the kinetics of transmutation by using a moderated spectrum. The moderator materials will be 11 B 4 C and CaH 2 for ECRIX-B and ECRIXH respectively, the irradiation conditions have been predicted for both the neutronics and thermal. The targets (MgO-AmO X pellets) are manufactured in the ATALANTE laboratory and the design is performed according to the PHENIX operating conditions. (authors)

  15. Consultants’ Meeting (Preparatory Meeting) on the IAEA Coordinated Research Project (CRP) “PHENIX End-of-Life Tests”. Working Material

    International Nuclear Information System (INIS)

    2008-01-01

    The overall objective of the CRP is to improve/validate the Member States' analytical capabilities in the field of fast reactor simulation and design. A necessary condition towards achieving this objective is a wide international verification and validation effort of the analysis methodology and codes currently employed in the fields of fast reactor neutronics, thermal hydraulics and plant dynamics to achieve enhanced safety. Therefore, in providing the required wide international basis of interested Member States, each applying different methodologies, the CRP will contribute towards achieving the stated objective with the help of benchmark exercises focusing on the experimental results obtained during the planned PHENIX End-of-Life (EOL) Tests

  16. Fast breeder reactor fuel reprocessing in France

    International Nuclear Information System (INIS)

    Bourgeois, M.; Le Bouhellec, J.; Eymery, R.; Viala, M.

    1984-08-01

    Simultaneous with the effort on fast breeder reactors launched several years ago in France, equivalent investigations have been conducted on the fuel cycle, and in particular on reprocessing, which is an indispensable operation for this reactor. The Rapsodie experimental reactor was associated with the La Hague reprocessing plant AT1 (1 kg/day), which has reprocessed about one ton of fuel. The fuel from the Phenix demonstration reactor is reprocessed partly at the La Hague UP2 plant and partly at the Marcoule pilot facility, undergoing transformation to reprocess all the fuel (TOR project, 5 t/y). The fuel from the Creys Malville prototype power plant will be reprocessed in a specific plant, which is in the design stage. The preliminary project, named MAR 600 (50 t/y), will mobilize a growing share of the CEA's R and D resources, as the engineering needs of the UP3 ''light water'' plant begins to decline. Nearly 20 tonnes of heavy metals irradiated in fast breeder reactors have been processed in France, 17 of which came from Phenix. The plutonium recovered during this reprocessing allowed the power plant cycle to be closed. This power plant now contains approximately 140 fuel asemblies made up with recycled plutonium, that is, more than 75% of the fuel assemblies in the Phenix core

  17. Radioisotopes in the primary circuit of a fast reactor

    International Nuclear Information System (INIS)

    Berlin, M.; Cauvin, M.

    1976-01-01

    In the frame of the research performed to understand the behaviour of the radioactive isotopes of iodine in the primary coolant circuit of fast reactor, a simple theoretical model is proposed. Results concerning PHENIX and RAPSODIE are given

  18. The French post irradiation examination database for the validation of depletion calculation tools

    International Nuclear Information System (INIS)

    Roque, Benedicte; Marimbeau, Pierre; Bioux, Philippe; Toubon, Herve; Daudin, Lucien

    2003-01-01

    This paper presents the experimental programmes conducted in France by the Commissariat a l'Energie Atomique (CEA) in order to validate spent fuel inventory calculations for core studies as well as fuel cycle studies. This large experimental programme was obtained in collaboration with our French partners, Electricite de France (EDF), FRAMATOME-ANP and COGEMA. The experimental data are based on chemical analysis measurements from fuel rod cuts irradiated in French reactors for PWR-UOx and MOx fuels, then dissolved in CEA laboratories, and from full assembly dissolutions at the COGEMA/La Hague reprocessing plants for UOx fuels. This enables us to cover a large range of UOx fuels with various enrichments in 235 U, 3.1% to 4.5%, associated with burnups from 10 GWd/t to 60 GWd/t. Recently, MOx fuels have also been investigated, with an initial Pu amount in the central zone of 5.6% and a maximum burnup of 45 GWd/t. Uranium, Plutonium, Americium, Curium isotopes and some fission products were analysed. Furthermore, Fission Products involved in Burn up Credit studies were measured. The experimental database contains also data for Boiling Water Reactor (BWR) with irradiated samples of BWR 9x9 and full BWR assemblies dissolutions. Furthermore some data exist for Fast Breeder Reactor (FBR) with small samples irradiated in the PHENIX reactor. An overview of ongoing programmes is also presented. (author)

  19. Algorithmic developments and qualification of the ERANOS nuclear code and data system for the characterization of fast neutron reactors

    International Nuclear Information System (INIS)

    Rimpault, G.

    2003-09-01

    In this report, the author discusses the algorithmic and methodological developments in the field of nuclear reactor physics, and more particularly the developments of the ERALIB1/ERANOS nuclear code and data system for the calculation of core critical mass and power of sodium-cooled fast neutron reactors (Phenix and Super Phenix), and of the CAPRA 4/94 core. After a brief recall of nuclear data and methods used to determine critical masses and powers, the author discusses the interpretation of start-up experiments performed on Super-Phenix. The methodology used to characterize the uncertainties of these parameters is then applied to the calculation of the Super-Phenix critical mass and power distribution. He presents the approach chosen to define the validity domain of the ERANOS form

  20. The reactor Phenix - cartridge rupture detection

    International Nuclear Information System (INIS)

    Graftieaux, J.

    1967-01-01

    This report defines the role of cartridge rupture detection in the reactor Phenix. It gives the possible methods, their probable performances, their advantages and disadvantages. The final form of the installation will be determined mainly by the degree of safety required, by the technical possibilities of the reactor design and by the operational flexibility wanted. (author) [fr

  1. Fuel and target programs for the transmutation at Phenix and other reactors; Programmes combustibles et cibles pour la transmutation dans Phenix et autres reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    Gaillard-Groleas, G

    2002-07-01

    The fuels and targets program for transmutation, performed in the framework of the axis 1 of the December 1991 law about the researches on the management of long-lived radioactive wastes, is in perfect consistency with the transmutation scenario studies carried out in the same framework. These studies put forward the advantage of fast breeder reactors (FBR) in the incineration of minor actinides and long-lived fission products. The program includes exploratory and technological demonstration studies covering the different design options. It aims at enhancing our knowledge of the behaviour of materials under irradiation and at ensuring the mastery of processes. The goals of the different experiments foreseen at Phenix reactor are presented. The main goal is to supply a set of results allowing to precise the conditions of the technical feasibility of minor actinides and long-lived fission products incineration in FBRs. (J.S.)

  2. Exploring the QCD Vacuum with Phenix

    Science.gov (United States)

    Barish, Kenneth N.

    2001-04-01

    The Relativistic Heavy Ion Collider at Brookhaven National Laboratory opens the possibility of exploring the "simple" vacuum of the early universe where quarks are not confined to color neutral bags and chirality is a good symmetry. In this talk1 I discuss PHENIX's capabilities to experimentally probe deconfinement with heavy quark bound state suppression and chirality with light vector mesons.

  3. Iterative model building, structure refinement and density modification with the PHENIX AutoBuild wizard

    International Nuclear Information System (INIS)

    Terwilliger, Thomas C.; Grosse-Kunstleve, Ralf W.; Afonine, Pavel V.; Moriarty, Nigel W.; Zwart, Peter H.; Hung, Li-Wei; Read, Randy J.; Adams, Paul D.

    2008-01-01

    The highly automated PHENIX AutoBuild wizard is described. The procedure can be applied equally well to phases derived from isomorphous/anomalous and molecular-replacement methods. The PHENIX AutoBuild wizard is a highly automated tool for iterative model building, structure refinement and density modification using RESOLVE model building, RESOLVE statistical density modification and phenix.refine structure refinement. Recent advances in the AutoBuild wizard and phenix.refine include automated detection and application of NCS from models as they are built, extensive model-completion algorithms and automated solvent-molecule picking. Model-completion algorithms in the AutoBuild wizard include loop building, crossovers between chains in different models of a structure and side-chain optimization. The AutoBuild wizard has been applied to a set of 48 structures at resolutions ranging from 1.1 to 3.2 Å, resulting in a mean R factor of 0.24 and a mean free R factor of 0.29. The R factor of the final model is dependent on the quality of the starting electron density and is relatively independent of resolution

  4. 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

  5. Assessment of the high temperature fission chamber technology for the French fast reactor program

    Energy Technology Data Exchange (ETDEWEB)

    Jammes, C.; Filliatre, P.; Geslot, B.; Domenech, T.; Normand, S. [Commissariat a l' Energie Atomique, CEA (France)

    2011-07-01

    High temperature fission chambers are key instruments for the control and protection of the sodium-cooled fast reactor. First, the developments of those neutron detectors, which are carried out either in France or abroad are reviewed. Second, the French realizations are assessed with the use of the technology readiness levels in order to identify tracks of improvement. (authors)

  6. Utilization of computerized techniques in important systems for safety. Super Phenix: reactor core temperature monitoring by microprocessors. Particular aspects related to safety requirements

    International Nuclear Information System (INIS)

    Berlin, C.; Pinoteau, J.

    1984-11-01

    The system of Fast Treatment of the Core Temperatures (TRTC) of SUPER PHENIX, is included in the Rector Protection system. The present communication gives the elements taken into account for the design of the system, as well from the material point of view, as from the software point of view, to satisfy the requirements imposed on the computers used in the protection system of a nuclear reactor [fr

  7. Cleaning and decontamination: Experimental feedback from PHENIX

    International Nuclear Information System (INIS)

    Masse, F.; Rodriguez, G.

    1997-01-01

    After the first few years of operation of PHENIX, it proved necessary to clean, then decontaminate sodium-polluted components, particularly large components such as the intermediate heat exchangers (IHX) and the primary pumps (PP). Ibis document presents the evolution of the cleaning and decontamination processes used, and specifies the reasons for this evolution. As regards the cleaning, experimental feedback and a greater rigour with respect to the hydrogen hazard have resulted in a modification of the process. The new cleaning process used at present (since 1994) is described in greater detail in this document. The main steps are: cold CO 2 bubbling in water, followed by hot CO 2 bubbling, spraying phase, then drying for inspection before immersion. In order to optimize and validate the process, the cleaning and decontamination plant has been highly instrumented, which, in particular, has allowed confirmation of the contention that the major part of the sodium is eliminated during the bubbling phases. With respect to decontamination, the objective is to perfect an efficient process that allows both human intervention with no particular biological shield for repair or maintenance of the components, and requalification of the materials after the decontamination operation. Owing to the high operating temperature of Fast Breeder Reactor components (400 to 550 deg. C), the activated corrosion products deposited on the components melt into the metal. The decontamination process therefore consists in either dissolving the deposits on the surface, or dissolving a thickness of about less than ten micrometers of the base metal. The reference process for austenitic-type steels is the SPm process, which consists in immersing the component in a sulphuric-phosphoric bath (sulphuric acid and phosphoric acid) at a temperature of 60 deg. C for 6 hours. The problem linked to this process is the treatment of the effluents that are produced, particularly phosphate releases. A

  8. Two neural network based strategies for the detection of a total instantaneous blockage of a sodium-cooled fast reactor

    International Nuclear Information System (INIS)

    Martinez-Martinez, Sinuhe; Messai, Nadhir; Jeannot, Jean-Philippe; Nuzillard, Danielle

    2015-01-01

    The total instantaneous blockage (TIB) of an assembly in the core of a sodium-cooled fast reactor (SFR) is investigated. Such incident could appear as an abnormal rise in temperature on the assemblies neighbouring the blockage. Its detection relies on a dataset of temperature measurements of the assemblies making up the core of the French Phenix Nuclear Reactor. The data are provided by the French Commission of Atomic and Alternatives Energies (CEA). Here, two strategies are proposed depending on whether the sensor measurement of the suspected assembly is reliable or not. The proposed methodology implements a time-lagged feed-forward neural (TLFFN) Network in order to predict the one-step-ahead temperature of a given assembly. The incident is declared if the difference between the predicted process and the actual one exceeds a threshold. In these simulated conditions, the method is efficient to detect small gradients as expected in reality. - Highlights: • We study the total instantaneous blockage (TIB) of a sodium-cooled fast reactor. • The TIB symptom is simulated as an abrupt rise on temperature (0.1–1 °C/s). • The goal is to improve the early detection of the incident. • Two strategies laying on neural networks are proposed. • TIB is detected in 3 s for 1 °C/s and 18–21 s for 0.1 °C/s

  9. French For Dummies

    CERN Document Server

    Erotopoulos; Williams, Michelle M; Wenzel, Dominique

    2011-01-01

    The fast, informal way to learn to speak French French is known as perhaps the most beautiful of all languages. Listen to someone speak French-sure, you don't have a clue what they're saying, but aren't you enraptured by the sound of it? French is a beautiful language but quite difficult to learn. Whether you need to learn the language for a French class, or you travel overseas for business or leisure, this revised edition of French for Dummies can help. Written in an easy-to-follow format, it gives you just what you need for basic communication in FrenchExpanded coverage of necessary grammar,

  10. Influence of various stresses on diametral and axial plastic deformations of the Phenix reactor fuel cans

    International Nuclear Information System (INIS)

    Guerin, Y.; Boutard, J.L.

    1983-04-01

    Dimensions of fuel cans are modified during irradiation in fast reactors: diameter increase is produced by steel swelling and irradiation creep under the pressure of fission gases and length increase integrates swelling. Diameter and density measured on fuel cans in SS 316, irradiated in the Phenix reactor, show that interaction spacer-can and interaction between pins produce plastic deformations. The interaction spacer-can leads not only to a helical deflection of the pin but also a slight axial plastic compression associated to a diametral plastic deformation. There is also a leveling of elongation in these strained pins because of friction with neighbouring pins [fr

  11. TRACE analysis of Phenix core response to an increase of the core inlet sodium temperature

    Energy Technology Data Exchange (ETDEWEB)

    Chenu, A., E-mail: aurelia.chenu@psi.ch [Paul Scherrer Inst., Villigen PSI (Switzerland); Ecole Polytechnique Federale (Switzerland); Mikityuk, K., E-mail: konstantin.mikityuk@psi.ch [Paul Scherrer Inst., Villigen PSI (Switzerland); Adams, R., E-mail: robert.adams@psi.ch [Paul Scherrer Inst., Villigen PSI (Switzerland); Eidgenossische Technische Hochschule, Zurich (Switzerland); Chawla, R., E-mail: rakesh.chawla@epfl.ch [Paul Scherrer Inst., Villigen PSI (Switzerland); Ecole Polytechnique Federale (Switzerland)

    2011-07-01

    This work presents the analysis, using the TRACE code, of the Phenix core response to an inlet sodium temperature increase. The considered experiment was performed in the frame of the Phenix End-Of-Life (EOL) test program of the CEA, prior to the final shutdown of the reactor. It corresponds to a transient following a 40°C increase of the core inlet temperature, which leads to a power decrease of 60%. This work focuses on the first phase of the transient, prior to the reactor scram and pump trip. First, the thermal-hydraulic TRACE model of the core developed for the present analysis is described. The kinetic parameters and feedback coefficients for the point kinetic model were first derived from a 3D static neutronic ERANOS model developed in a former study. The calculated kinetic parameters were then optimized, before use, on the basis of the experimental reactivity in order to minimize the error on the power calculation. The different reactivity feedbacks taken into account include various expansion mechanisms that have been specifically implemented in TRACE for analysis of fast-neutron spectrum systems. The point kinetic model has been used to study the sensitivity of the core response to the different feedback effects. The comparison of the calculated results with the experimental data reveals the need to accurately calculate the reactivity feedback coefficients. This is because the reactor response is very sensitive to small reactivity changes. This study has enabled us to study the sensitivity of the power change to the different reactivity feedbacks and define the most important parameters. As such, it furthers the validation of the FAST code system, which is being used to gain a more in-depth understanding of SFR core behavior during accidental transients. (author)

  12. The PHENIX experiment at RHIC

    Energy Technology Data Exchange (ETDEWEB)

    Tonse, S.R.; Thomas, J.H.

    1993-12-15

    Later this decade the Relativistic Heavy Ion Collider (RHIC) will be built at Brookhaven National Laboratory. Its goal will be to accelerate and collide Au beams at 100 GeV/c in an attempt to create a Quark Gluon Plasma (QGP). The PHENIX detector aims to detect the QGP through its leptonic and hadronic signatures. We describe here its physics capabilities and the details of the apparatus designed to pick out rare leptonic signatures from among hadronic multiplicities of up to 1500 particles per unit of rapidity.

  13. Application of pattern recognition techniques to the detection of the Phenix reactor control rods vibrations

    International Nuclear Information System (INIS)

    Zwingelstein, G.; Deat, M.; Le Guillou, G.

    1979-01-01

    The incipient detection of control rods vibrations is very important for the safety of the operating plants. This detection can be achieved by an analysis of the peaks of the power spectrum density of the neutron noise. Pattern Recognition techniques were applied to detect the rod vibrations which occured at the fast breeder Phenix (250MWe). In the first part we give a description of the basic pattern which is used to characterize the behavior of the plant. The pattern is considered as column vector in n dimensional Euclidian space where the components are the samples of the power spectral density of the neutron noise. In the second part, a recursive learning procedure of the normal patterns which provides the mean and the variance of the estimates is described. In the third part the classification problem has been framed in terms of a partitioning procedure in n dimensional space which encloses regions corresponding to normal operations. This pattern recognition scheme was applied to the detection of rod vibrations with neutron data collected at the Phenix site before and after occurence of the vibrations. The analysis was carried out with a 42-dimensional measurement space. The learned pattern was estimated with 150 measurement vectors which correspond to the period without vibrations. The efficiency of the surveillance scheme is then demonstrated by processing separately 119 measurement vectors recorded during the rod vibration period

  14. Measurement of the fuel temperature and the fuel-to-coolant heat transfer coefficient of Super Phenix 1 fuel elements

    International Nuclear Information System (INIS)

    Edelmann, M.

    1995-12-01

    A new measurement method for measuring the mean fuel temperature as well as the fuel-to-coolant heat transfer coefficient of fast breeder reactor subassemblies (SA) is reported. The method is based on the individual heat balance of fuel SA's after fast reactor shut-downs and uses only the plants normal SA outlet temperature and neutron power signals. The method was used successfully at the french breeder prototype Super Phenix 1. The mean SA fuel temperature as well as the heat transfer coefficient of all SPX SA's have been determined at power levels between 15 and 90% of nominal power and increasing fuel burn-up from 3 to 83 EFPD (Equivalent of Full Power-Days). The measurements also provided fuel and whole SA time constants. The estimated accuracy of measured fuel parameters is in the order of 10%. Fuel temperatures and SA outlet temperature transients were also calculated with the SPX1 systems code DYN2 for exactly the same fuel and reactor operating parameters as in the experiments. Measured fuel temperatures were higher than calculated ones in all cases. The difference between measured and calculated core mean values increases from 50 K at low power to 180 K at 90% n.p. This is about the double of the experimental error margins. Measured SA heat transfer coefficients are by nearly 20% lower than corresponding heat transfer parameters used in the calculations. Discrepancies found between measured and calculated results also indicate that either the transient heat transfer in the gap between fuel and cladding (gap conductance) might not be exactly reproduced in the computer code or that the gap in the fresh fuel was larger than assumed in the calculations. (orig.) [de

  15. Re-interpretation of the ERMINE-V experiment validation of fission product integral cross section in the fast energy range

    Science.gov (United States)

    Ros, Paul; Leconte, Pierre; Blaise, Patrick; Naymeh, Laurent

    2017-09-01

    The current knowledge of nuclear data in the fast neutron energy range is not as good as in the thermal range, resulting in larger propagated uncertainties in integral quantities such as critical masses or reactivity effects. This situation makes it difficult to get the full benefit from recent advances in modeling and simulation. Zero power facilities such as the French ZPR MINERVE have already demonstrated that they can contribute to significantly reduce those uncertainties thanks to dedicated experiments. Historically, MINERVE has been mainly dedicated to thermal spectrum studies. However, experiments involving fast-thermal coupled cores were also performed in MINERVE as part of the ERMINE program, in order to improve nuclear data in fast spectra for the two French SFRs: PHENIX and SUPERPHENIX. Some of those experiments have been recently revisited. In particular, a full characterization of ZONA-1 and ZONA-3, two different cores loaded in the ERMINE V campaign, has been done, with much attention paid to possible sources of errors. It includes detailed geometric descriptions, energy profiles of the direct and adjoint fluxes and spectral indices obtained thanks to Monte Carlo calculations and compared to a reference fast core configuration. Sample oscillation experiments of separated fission products such as 103Rh or 99Tc, which were part of the ERMINE V program, have been simulated using recently-developed options in the TRIPOLI-4 code and compared to the experimental values. The present paper describes the corresponding results. The findings motivate in-depth studies for designing optimized coupled-core conditions in ZEPHYR, a new ZPR which will replace MINERVE and will provide integral data to meet the needs of Gen-III and Gen-IV reactors.

  16. Analysis of Phenix End-of-Life asymmetry test with multi-dimensional pool modeling of MARS-LMR code

    International Nuclear Information System (INIS)

    Jeong, H.-Y.; Ha, K.-S.; Choi, C.-W.; Park, M.-G.

    2015-01-01

    Highlights: • Pool behaviors under asymmetrical condition in an SFR were evaluated with MARS-LMR. • The Phenix asymmetry test was analyzed one-dimensionally and multi-dimensionally. • One-dimensional modeling has limitation to predict the cold pool temperature. • Multi-dimensional modeling shows improved prediction of stratification and mixing. - Abstract: The understanding of complicated pool behaviors and its modeling is essential for the design and safety analysis of a pool-type Sodium-cooled Fast Reactor. One of the remarkable recent efforts on the study of pool thermal–hydraulic behaviors is the asymmetrical test performed as a part of Phenix End-of-Life tests by the CEA. To evaluate the performance of MARS-LMR code, which is a key system analysis tool for the design of an SFR in Korea, in the prediction of thermal hydraulic behaviors during an asymmetrical condition, the Phenix asymmetry test is analyzed with MARS-LMR in the present study. Pool regions are modeled with two different approaches, one-dimensional modeling and multi-dimensional one, and the prediction results are analyzed to identify the appropriateness of each modeling method. The prediction with one-dimensional pool modeling shows a large deviation from the measured data at the early stage of the test, which suggests limitations to describe the complicated thermal–hydraulic phenomena. When the pool regions are modeled multi-dimensionally, the prediction gives improved results quite a bit. This improvement is explained by the enhanced modeling of pool mixing with the multi-dimensional modeling. On the basis of the results from the present study, it is concluded that an accurate modeling of pool thermal–hydraulics is a prerequisite for the evaluation of design performance and safety margin quantification in the future SFR developments

  17. Apparatus for ultrasonic visualization in sodium (VISUS) and acoustic detection in the Phenix reactor

    International Nuclear Information System (INIS)

    Lions, M.; Berger, R.; Bret, A.; Buis, H.; Barton, J.

    A description is given of two acoustic monitoring systems studied at the Fast Neutron Reactor Department at CEN/Cadarache and used in the Phenix reactor. The first is the active type, and the second, passive. The active apparatus is based on the sonar principle and permits visualizing objects inside a reactor tank, especially the heads of assemblies during handling. The passive apparatus, the acoustic detector, observes the reactor core by analyzing the acoustic noise produced in the reactor core. The electroacoustic converters are in both cases located outside, and the acoustic vibrations are transmitted by wave guides. The two pieces of apparatus can operate in a hostile environment, such as liquid metal at high temperature in the presence of high neutron and gamma fluxes

  18. Latest Results of Open Heavy Flavor and Quarkonia from the PHENIX Experiment at RHIC

    International Nuclear Information System (INIS)

    Nouicer, Rachid

    2017-01-01

    The PHENIX Collaboration carries out a comprehensive physics program which studies heavy flavor production in relativistic heavy ion collisions at RHIC. The discovery at RHIC of large high-p T suppression and flow of electrons from heavy quarks flavors have altered our view of the hot and dense matter formed in central Au+Au collisions at GeV. These results suggest a large energy loss and flow of heavy quarks in the hot, dense matter. In recent years, the PHENIX has installed a silicon vertex tracker both in central rapidity (VTX) and in forward rapidity (FVTX) regions, and has collected large data samples. These two silicon trackers enhance the capability of heavy flavor measurements via precision tracking. This paper summarizes some of the latest PHENIX results concerning open heavy flavor and quarkonia production as a function of rapidity, energy and system size. (paper)

  19. Coastal Amplification Laws for the French Tsunami Warning Center: Numerical Modeling and Fast Estimate of Tsunami Wave Heights Along the French Riviera

    Science.gov (United States)

    Gailler, A.; Hébert, H.; Schindelé, F.; Reymond, D.

    2018-04-01

    Tsunami modeling tools in the French tsunami Warning Center operational context provide rapidly derived warning levels with a dimensionless variable at basin scale. A new forecast method based on coastal amplification laws has been tested to estimate the tsunami onshore height, with a focus on the French Riviera test-site (Nice area). This fast prediction tool provides a coastal tsunami height distribution, calculated from the numerical simulation of the deep ocean tsunami amplitude and using a transfer function derived from the Green's law. Due to a lack of tsunami observations in the western Mediterranean basin, coastal amplification parameters are here defined regarding high resolution nested grids simulations. The preliminary results for the Nice test site on the basis of nine historical and synthetic sources show a good agreement with the time-consuming high resolution modeling: the linear approximation is obtained within 1 min in general and provides estimates within a factor of two in amplitude, although the resonance effects in harbors and bays are not reproduced. In Nice harbor especially, variation in tsunami amplitude is something that cannot be really assessed because of the magnitude range and maximum energy azimuth of possible events to account for. However, this method is well suited for a fast first estimate of the coastal tsunami threat forecast.

  20. PHENIX Spinfest School 2009 at BNL

    Energy Technology Data Exchange (ETDEWEB)

    Foster,S.P.; Foster,S.; Seidl, R.; Goto, Y.; Okada, K.

    2009-08-07

    Since 2005, the PHENIX Spin Physics Working Group has set aside several weeks each summer for the purposes of training and integrating recent members of the working group as well as coordinating and making rapid progress on support tasks and data analysis. One week is dedicated to more formal didactic lectures by outside speakers. The location has so far alternated between BNL and the RIKEN campus in Wako, Japan, with support provided by RBRC and LANL.

  1. Breeders: operational experience with fast power reactors in five states - more intensive German-French breeder cooperation

    International Nuclear Information System (INIS)

    Hueper, R.

    1978-01-01

    In the past year contracts have been signed and implemented for German-French cooperation in LMFBR development and commercialization. - The first German nuclear power station with a sodium cooled fast reactor, KNK II in Karlsruhe, is going into operation. - Construction of the prototype SNR 300 at Kalkar (Lower Rhine) is slowing down awaiting a decision of the German Federal Constitutional Court. - On the international level, remarkable experience in the operation of fast power reactors has accumulated. - Possible fuel cycle alternatives are being evaluated by an international committee. (orig.) [de

  2. Design and Beam Test Results for the sPHENIX Electromagnetic and Hadronic Calorimeter Prototypes

    OpenAIRE

    Aidala, C. A.; Bailey, V.; Beckman, S.; Belmont, R.; Biggs, C.; Blackburn, J.; Boose, S.; Chiu, M.; Connors, M.; Franz, A.; Haggerty, J. S.; He, X.; Higdon, M. M.; Huang, J.; Kauder, K.

    2017-01-01

    The sPHENIX experiment at the Relativistic Heavy Ion Collider (RHIC) will perform high precision measurements of jets and heavy flavor observables for a wide selection of nuclear collision systems, elucidating the microscopic nature of strongly interacting matter ranging from nucleons to the strongly coupled quark-gluon plasma. A prototype of the sPHENIX calorimeter system was tested at the Fermilab Test Beam Facility as experiment T-1044 in the spring of 2016. The electromagnetic calorimeter...

  3. Fuel and target programs for the transmutation at Phenix and other reactors

    International Nuclear Information System (INIS)

    Gaillard-Groleas, G.

    2002-01-01

    The fuels and targets program for transmutation, performed in the framework of the axis 1 of the December 1991 law about the researches on the management of long-lived radioactive wastes, is in perfect consistency with the transmutation scenario studies carried out in the same framework. These studies put forward the advantage of fast breeder reactors (FBR) in the incineration of minor actinides and long-lived fission products. The program includes exploratory and technological demonstration studies covering the different design options. It aims at enhancing our knowledge of the behaviour of materials under irradiation and at ensuring the mastery of processes. The goals of the different experiments foreseen at Phenix reactor are presented. The main goal is to supply a set of results allowing to precise the conditions of the technical feasibility of minor actinides and long-lived fission products incineration in FBRs. (J.S.)

  4. European R and D co-ordinate programme on structural integrity of fast breeder reactors

    International Nuclear Information System (INIS)

    Hoffmann, A.; Combescure, A.; Acker, D.; Corsi, F.; Martelli, A.; Vinzens, K.; Angerbauer, A.

    1989-01-01

    After a period of development of medium size prototype plants, PFR in United Kingdom, Phenix in France and SNR 300 in West Germany, and the build up of the large size prototype plant Super Phenix in France by the European Consortium, NERSA, Belgium, France, Italy, United Kingdom and West Germany decided to join their efforts in order to pursue the development of LMFBR nuclear power plants. This paper presents the European Research and Development coordinated program in the field of structural integrity of fast breeder reactors with its organization, its objectives, its programs and the resources allocated for development. (author)

  5. The behaviour of Phenix fuel pin bundle under irradiation

    International Nuclear Information System (INIS)

    Marbach, G.; Millet, P.; Blanchard, P.; Huillery, R.

    1979-07-01

    An entire Phenix sub-assembly has been mounted and sectioned after irradiation. The examination of cross-sections revealed the effects of mechanical interaction in the bundle (ovalisations and contacts between clads). According to analysis of the sodium channels, cooling of the pin bundle remained uniform. (author)

  6. A flexible analog memory address list manager for PHENIX

    International Nuclear Information System (INIS)

    Ericson, M.N.; Musrock, M.S.; Britton, C.L. Jr.; Walker, J.W.; Wintenberg, A.L.; Young, G.R.; Allen, M.D.

    1996-01-01

    A programmable analog memory address list manager has been developed for use with all analog memory-based detector subsystems of PHENIX. The unit provides simultaneous read/write control, cell write-over protection for both a Level-1 trigger decision delay and digitization latency, and re-ordering of AMU addresses following conversion, at a beam crossing rate of 105 ns. Addresses are handled such that up to 5 Level-1 (LVL-1) events can be maintained in the AMU without write-over. Data tagging is implemented for handling overlapping and shared beam-event data packets. Full usage in all PHENIX analog memory-based detector subsystems is accomplished by the use of detector-specific programmable parameters--the number of data samples per valid LVL-1 trigger and the sample spacing. Architectural candidates for the system are discussed with emphasis on implementation implications. Details of the design are presented including application specifics, timing information, and test results from a full implementation using field programmable gate arrays (FPGAs)

  7. Iterative model-building, structure refinement, and density modification with the PHENIX AutoBuild Wizard

    Energy Technology Data Exchange (ETDEWEB)

    Los Alamos National Laboratory, Mailstop M888, Los Alamos, NM 87545, USA; Lawrence Berkeley National Laboratory, One Cyclotron Road, Building 64R0121, Berkeley, CA 94720, USA; Department of Haematology, University of Cambridge, Cambridge CB2 0XY, England; Terwilliger, Thomas; Terwilliger, T.C.; Grosse-Kunstleve, Ralf Wilhelm; Afonine, P.V.; Moriarty, N.W.; Zwart, P.H.; Hung, L.-W.; Read, R.J.; Adams, P.D.

    2007-04-29

    The PHENIX AutoBuild Wizard is a highly automated tool for iterative model-building, structure refinement and density modification using RESOLVE or TEXTAL model-building, RESOLVE statistical density modification, and phenix.refine structure refinement. Recent advances in the AutoBuild Wizard and phenix.refine include automated detection and application of NCS from models as they are built, extensive model completion algorithms, and automated solvent molecule picking. Model completion algorithms in the AutoBuild Wizard include loop-building, crossovers between chains in different models of a structure, and side-chain optimization. The AutoBuild Wizard has been applied to a set of 48 structures at resolutions ranging from 1.1 {angstrom} to 3.2 {angstrom}, resulting in a mean R-factor of 0.24 and a mean free R factor of 0.29. The R-factor of the final model is dependent on the quality of the starting electron density, and relatively independent of resolution.

  8. Super Phenix 1: in Service inspection of main and safety tanks weldments

    International Nuclear Information System (INIS)

    Asty, Michel; Vertut, Jean; Argous, J.P.

    1980-05-01

    In service inspection of the main tank of the Super Phenix 1 reactor is a new demand as compared to Phenix: the authorities have asked that surface and internal defects could be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks

  9. Super Phenix 1: In-service inspection of main and safety tanks weldments

    Energy Technology Data Exchange (ETDEWEB)

    Asty, M [DTech/STA, Centre d' Etudes Nucleaires de Saclay (France); Vertut, J [DPR/STEP, Centre d' Etudes Nucleaires de Saclay (France); Argous, J P [DRNR/STRS, Centre d' Etudes Nucleaires de Cadarache (France)

    1980-11-01

    In Service Inspection of the main tank of the Super Phenix 1 reactor is a new demand compared to Phenix: the authorities have asked that surface and internal defects be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks. (author)

  10. Super Phenix 1: In-service inspection of main and safety tanks weldments

    International Nuclear Information System (INIS)

    Asty, M.; Vertut, J.; Argous, J.P.

    1980-01-01

    In Service Inspection of the main tank of the Super Phenix 1 reactor is a new demand compared to Phenix: the authorities have asked that surface and internal defects be detected and their evolution monitored in the future. The presence of thermal baffles inside the main tank precludes the access on that side: the distance between the main and safety tanks takes into account the room needed for an In Service Inspection module. An inspection vehicle is presently under development, which includes ultrasonic examination (focussed probes) and visual examination (TV cameras) capabilities. We briefly describe the techniques that have been selected for ultrasonic testing and also for the vehicle and its guidance between the tanks. (author)

  11. TECHNICAL DESIGN REPORT FOR A NOSECONE CALORIMETER (NCC) FOR THE PHENIX EXPERIMENT.

    Energy Technology Data Exchange (ETDEWEB)

    PHENIX EXPERIMENT; OBRIEN,E.; BOOSE, S.; CHIU, M.; JOHNSON, B.M.; KISTENEV, E.P.; LYNCH, D.; NOUICER, R.; PAK, R.; PISANI, R.; STOLL, S.P.; SUKHANOV, A.; WOODY, C.L.; LI, Z.; RADEKA, V.; RESCIA, S.; (PHENIX EXPERIMENT COLLABORATORS)

    2007-08-01

    A remarkable result has emerged from the first several years of data taking at RHIC--the high temperature and density phase of QCD matter created in heavy ion collisions at RHIC is best described as a near perfect fluid--the strongly interacting Quark-Gluon-Plasma (sQGP). This state is characterized by a small viscosity to entropy ratio, and a high density of color charges which induces huge energy losses of partons transversing the medium. The task for the future is to understand the characteristics of the sQGP, and perhaps more importantly--to gain some insight into how and why such a medium is created. The PHENIX detector has been one of the primary experimental tools at RHIC; in particular the electromagnetic calorimeter has been a critical component of many of the measurements leading to this discovery. The coverage of the present PHENIX electromagnetic calorimeter is rather limited, covering half the azimuth and -0.35< {eta} <0.35 Further progress requires larger coverage of electromagnetic calorimetry, both to increase the rate for low cross section phenomena, and to cover a broader range of pseudorapidity to study the rapidity dependence of the medium. A pair of Nosecone Calorimeters (NCC) has been designed covering both positive and negative rapidity regions 1< |{eta}| <3 of the PHENIX detector. The NCC will make it possible to perform tomographic studies of the jet energy dependence of energy loss and medium response, by using direct photons as trigger particles over a large rapidity range. The technique of correlating trigger hadrons with low momentum hadrons has been powerfully exploited at RHIC to study the evolution of back to back jets [1, 2] and hence the response of the medium. The NCC will make it possible to do such studies using direct photons as the trigger particles. The direct photon in such ''photon-jet'' events tags the transverse momentum of outgoing parton which then fragments into lower energy particles. Together with

  12. Blind post-test analysis of Phenix End-of-Life natural circulation test with the MARS-LMR

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Kwon, Young Min; Chang, Won Pyo; Suk, Su Dong; Lee, Kwi Lim

    2010-01-01

    KAERI is developing a system analysis code, MARS-LMR, for the application to a sodium-cooled fast reactor (SFR). This code will be used as a basic tool in the design and analysis of future SFR systems in Korea. Before wide application of a system analysis code, it is required to verify and validate the code models through analyses for appropriate experimental data or analytical results. The MARS-LMR code has been developed from MARS code which had been well verified and validated for a pressurized water reactor (PWR) system. The MARS-LMR code shares the same form of governing equations and solution schemes with MARS code, which eliminates the need of independent verification procedure. However, it is required to validate the applicability of the code to an SFR system because it adopts some dedicated heat transfer models, pressure drop models, and material properties models for a sodium system. Phenix is a medium-sized pool-type SFR successfully operated for 35 years since 1973. This reactor reached its final shutdown in February 2009. An international program of Phenix end-of-life (EOL) test was followed and some valuable information was obtained from the test, which will be useful for the validation of SFR system analysis code. In the present study, the performance of MARS-LMR code is evaluated through a blind calculation with the boundary conditions measured in the real test. The post-test analysis results are also compared with the test data generated in the test

  13. PHENIX Conceptual Design Report. An experiment to be performed at the Brookhaven National Laboratory Relativistic Heavy Ion Collider

    Energy Technology Data Exchange (ETDEWEB)

    Nagamiya, Shoji; Aronson, Samuel H.; Young, Glenn R.; Paffrath, Leo

    1993-01-29

    The PHENIX Conceptual Design Report (CDR) describes the detector design of the PHENIX experiment for Day-1 operation at the Relativistic Heavy Ion Collider (RHIC). The CDR presents the physics capabilities, technical details, cost estimate, construction schedule, funding profile, management structure, and possible upgrade paths of the PHENIX experiment. The primary goals of the PHENIX experiment are to detect the quark-gluon plasma (QGP) and to measure its properties. Many of the potential signatures for the QGP are measured as a function of a well-defined common variable to see if any or all of these signatures show a simultaneous anomaly due to the formation of the QGP. In addition, basic quantum chromodynamics phenomena, collision dynamics, and thermodynamic features of the initial states of the collision are studied. To achieve these goals, the PHENIX experiment measures lepton pairs (dielectrons and dimuons) to study various properties of vector mesons, such as the mass, the width, and the degree of yield suppression due to the formation of the QGP. The effect of thermal radiation on the continuum is studied in different regions of rapidity and mass. The e{mu} coincidence is measured to study charm production, and aids in understanding the shape of the continuum dilepton spectrum. Photons are measured to study direct emission of single photons and to study {pi}{sup 0} and {eta} production. Charged hadrons are identified to study the spectrum shape, production of antinuclei, the {phi} meson (via K{sup +}K{sup {minus}} decay), jets, and two-boson correlations. The measurements are made down to small cross sections to allow the study of high p{sub T} spectra, and J/{psi} and {Upsilon} production. The PHENIX collaboration consists of over 300 scientists, engineers, and graduate students from 43 institutions in 10 countries. This large international collaboration is supported by US resources and significant foreign resources.

  14. Design and Beam Test Results for the sPHENIX Electromagnetic and Hadronic Calorimeter Prototypes

    Energy Technology Data Exchange (ETDEWEB)

    Aidala, C.A.; et al.

    2017-04-05

    The sPHENIX experiment at the Relativistic Heavy Ion Collider (RHIC) will perform high precision measurements of jets and heavy flavor observables for a wide selection of nuclear collision systems, elucidating the microscopic nature of strongly interacting matter ranging from nucleons to the strongly coupled quark-gluon plasma. A prototype of the sPHENIX calorimeter system was tested at the Fermilab Test Beam Facility as experiment T-1044 in the spring of 2016. The electromagnetic calorimeter (EMCal) prototype is composed of scintillating fibers embedded in a mixture of tungsten powder and epoxy. The hadronic calorimeter (HCal) prototype is composed of tilted steel plates alternating with plastic scintillator. Results of the test beam reveal the energy resolution for electrons in the EMCal is $2.8\\%\\oplus~15.5\\%/\\sqrt{E}$ and the energy resolution for hadrons in the combined EMCal plus HCal system is $13.5\\%\\oplus 64.9\\%/\\sqrt{E}$. These results demonstrate that the performance of the proposed calorimeter system is consistent with \\geant simulations and satisfies the sPHENIX specifications.

  15. Tritium and hydrogen behaviour at Phenix power plant. Application to development and validation of KUMAR type models

    International Nuclear Information System (INIS)

    Tibi, A.; Misraki, J.; Feron, D.

    1984-04-01

    Experimentations at Phenix reactor confirmed the fitness of the KUMAR model for predicting the behaviour of hydrogen and tritium, and thus, prevision of the tritium distribution at Super Phenix reactor: calculation of the tritium content of a regenerated secondary cold trap, behaviour of hydrogen during power operation, the primary cold trap being deliberately outage, and estimation of the tritium and hydrogen sources and permeation transfer ratios [fr

  16. MARS-LMR modeling for the post-test analysis of Phenix End-of-Life natural circulation

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Chang, Won Pyo; Lee, Kwi Lim

    2011-01-01

    For a successful design and analysis of Sodium cooled Fast Reactor (SFR), it is required to have a reliable and well-proven system analysis code. To achieve this purpose, KAERI is enhancing the modeling capability of MARS code by adding the SFR-specific models such as pressure drop model, heat transfer model and reactivity feedback model. This version of MARS-LMR will be used as a basic tool in the design and analysis of future SFR systems in Korea. Before wide application of MARS-LMR code, it is required to verify and validate the code models through analyses for appropriate experimental data or analytical results. The end-of-life test of Phenix reactor performed by the CEA provided a unique opportunity to have reliable test data which is very valuable in the validation and verification of a SFR system analysis code. The KAERI joined this international program of the analysis of Phenix end-of-life natural circulation test coordinated by the IAEA from 2008. The main test of natural circulation was completed in 2009. Before the test the KAERI performed the pre-test analysis based on the design condition provided by the CEA. Then, the blind post-test analysis was also performed based on the test conditions measured during the test before the CEA provide the final test results. Finally, the final post-test analysis was performed recently to predict the test results as accurate as possible. This paper introduces the modeling approach of the MARS-LMR used in the final post-test analysis and summarizes the major results of the analysis

  17. Coupled thermal-hydraulic and neutronic simulations of Phenix control rod withdrawal tests with SIMMER-IV

    International Nuclear Information System (INIS)

    Kriventsev, Vladimir; Gabrielli, Fabrizio; Rineiski, Andrei

    2014-01-01

    The “end-of-life” tests performed in the Phenix reactor before its final shutdown in 2009, in particular the Control Rod (CR) withdrawal experiments provide an excellent opportunity for the validation and verification of the reactor physics computer codes and modeling approaches. SIMMER-IV, a modern three-dimensional reactor safety code, has been recently employed at Karlsruhe Institute of Technology (KIT) for simulating Phenix experiments in the framework of a benchmark exercise organized under the IAEA project. In this paper, we report and discuss main results obtained with SIMMER-IV at KIT. Particular attention is devoted to the coupling features of thermal-hydraulics and neutronics and their mutual influences. The reactor reactivity, power and neutron flux distributions calculated with SIMMER-IV are in good agreement both with experimental results and with calculations with advanced neutronics codes, such as ERANOS, while the CR reactivity worth is overestimated due to neglecting heterogeneity effects. Because of its multi-physics capabilities SIMMER also calculates the temperature distributions which are in a good agreement with the experimental test results. In this work we describe the improvements in SIMMER neutronics model by employing a correction that is based on the results of cell calculations performed with ERANOS. The study confirms that the 3D SIMMER-IV code can accurately predict major fast reactor neutronics and thermal hydraulic parameters, provided that a special treatment is employed for CR modeling. The results of calculations are analyzed in frames of SIMMER-IV validation and verification assessment. (author)

  18. PROPOSAL FOR A SILICON VERTEX TRACKER (VTX) FOR THE PHENIX EXPERIMENT

    Energy Technology Data Exchange (ETDEWEB)

    AKIBA,Y.

    2004-10-01

    We propose the construction of a Silicon Vertex Tracker (VTX) for the PHENIX experiment at RHIC. The VTX will substantially enhance the physics capabilities of the PHENIX central arm spectrometers. Our prime motivation is to provide precision measurements of heavy-quark production (charm and beauty) in A+A, p(d)+A, and polarized p+p collisions. These are key measurements for the future RHIC program, both for the heavy ion program as it moves from the discovery phase towards detailed investigation of the properties of the dense nuclear medium created in heavy ion collisions, and for the exploration of the nucleon spin-structure functions. In addition, the VTX will also considerably improve other measurements with PHENIX. The main physics topics addressed by the VTX are: (1) Hot and dense strongly interacting matter--(a) Potential enhancement of charm production, (b) Open beauty production, (c) Flavor dependence of jet quenching and QCD energy loss, (d) Accurate charm reference for quarkonium, (e) Thermal dilepton radiation, (f) High p{sub T} phenomena with light flavors above 10-15 GeV/c in p{sub T}, and (g) Upsilon spectroscopy in the e{sup +}e{sup -} decay channel. (2) Gluon spin structure of the nucleon--(a) {Delta}G/G with charm, (b) {Delta}G/G with beauty, and (c) x dependence of {Delta}G/G with {gamma}-jet correlations. (3) Nucleon structure in nuclei--Gluon shadowing over broad x-range.

  19. A flexible analog memory address list manager/controller for PHENIX

    International Nuclear Information System (INIS)

    Ericson, M.N.; Walker, J.W.; Britton, C.L.; Wintenberg, A.L.; Young, G.R.

    1995-01-01

    A programmable analog memory address list manager/controller has been developed for use with all analog memory-based detector subsystems of PHENIX. The unit provides simultaneous read/write control, cell write-over protection for both a Level-1 trigger decision delay and digitization latency, and re-ordering of AMU addresses following conversion, at a beam crossing rate of 112 ns. Addresses are handled such that up to 5 Level-1 events can be maintained in the AMU without write-over. Data tagging is implemented for handling overlapping and shared beam event data packets. Full usage in all PHENIX analog memory-based detector sub-systems is accomplished by the use of detector-specific programmable parameters -- the number of data samples per Level-1 trigger valid and the swnple spacing. Architectural candidates for the system are discussed with emphasis on implementation implications. Details of the design are presented including design simulations, timing information, and test results from a full implementation using programmable logic devices

  20. Silicon vertex tracker for RHIC PHENIX experiment

    Energy Technology Data Exchange (ETDEWEB)

    Taketani, A [RIKEN, Nishina Ctr Accelerator Based Sci, Wako, Saitama, Japan; Cianciolo, Vince [ORNL; Enokizono, Akitomo [Oak Ridge National Laboratory (ORNL); PHENIX, Collaboration [The

    2010-01-01

    The PHENIX experiment at Relativistic Heavy Ion Collider will be equipped with Silicon Vertex tracker to enhance its physics capability. There are four layers of silicon sensor to reconstruct charged tracks with 50 {micro}m resolution of decay length measurement. The VTX surrounds the collision point. The inner two layers and the outer two layers are composed of 30 pixel ladders and 44 stripixel ladders, respectively. We have been developing these detectors and done a performance test with 120 GeV proton beam.

  1. Fast reactors

    International Nuclear Information System (INIS)

    Vasile, A.

    2001-01-01

    Fast reactors have capacities to spare uranium natural resources by their breeding property and to propose solutions to the management of radioactive wastes by limiting the inventory of heavy nuclei. This article highlights the role that fast reactors could play for reducing the radiotoxicity of wastes. The conversion of 238 U into 239 Pu by neutron capture is more efficient in fast reactors than in light water reactors. In fast reactors multi-recycling of U + Pu leads to fissioning up to 95% of the initial fuel ( 238 U + 235 U). 2 strategies have been studied to burn actinides: - the multi-recycling of heavy nuclei is made inside the fuel element (homogeneous option); - the unique recycling is made in special irradiation targets placed inside the core or at its surroundings (heterogeneous option). Simulations have shown that, for the same amount of energy produced (400 TWhe), the mass of transuranium elements (Pu + Np + Am + Cm) sent to waste disposal is 60,9 Kg in the homogeneous option and 204.4 Kg in the heterogeneous option. Experimental programs are carried out in Phenix and BOR60 reactors in order to study the feasibility of such strategies. (A.C.)

  2. Towards commercial fast breeder reactors the first 1200 MWe unit

    International Nuclear Information System (INIS)

    Banal, M.; Carle, R.

    The public probably thinks of these fast breeder reactors in terms of their rising unit capacity: RAPSODIE 20 MW (thermal), raised to 40 MW, PHENIX 25 MWe, and now 1200 MWe. However, the purposes of the project and the framework of construction have been fundamentally different in each case. Design parameters and the development program of the LMFBR are presented. (auth)

  3. Maintenance and repair of LMFBR steam generators

    International Nuclear Information System (INIS)

    Verriere, P.; Alanche, J.; Minguet, J.L.

    1984-06-01

    After some general remarks on the French fast neutron system, this paper presents the state of the program for the construction of fast reactor in France. Then, the general design of Super Phenix 1 steam generator components is outlined and, the in-service monitoring systems and protective devices with which they are equiped are briefly described. The methods used, in the event of leakage, for leak location, steam generator inspection, steam generator repair and putting the affected loop back into service, are discussed. There are two main lines of research, relating respectively to the means of water leak detection in sodium and the inspection arrangements that will be used either periodically, or following a sodium-water reaction. Finally, after a brief description of the steam generator, this paper describes the four incidents (leaks) that occurred on the Phenix steam generator in the course of 1982 and 1983, and the subsequent repair operations

  4. Chemical interaction between the oxide and the clad in PHENIX fuel at burnup up to 60,000 MWd/t

    International Nuclear Information System (INIS)

    Conte, M.; Marcon, J.P.

    1977-01-01

    In every fuel element there is a potential problem of chemical interaction between the fissile portion and the clad. As a matter of fact, even if the choice of materials is made after having established a satisfactory chemical compatibility between the fuel- (UO 2 (U,Pu)O 2 , (U,Pu) C, . . .) and the clad (stainless steel, zircaloy, . . . ) out of pile, it is difficult to guarantee this compatibility after operation in the reactor due, on one hand, to the presence of fission products and, on the other hand, to impurities which are always present in the fuel to a greater or lesser degree. The fuel element currently chosen for the sodium-cooled fast reactors ((U,Pu)O 2 in stainless steel clad) does not avoid this problem, in particular because of the relatively high temperatures envisioned for this type of reactor - the clad temperature is about 650 deg. C. Since it is considered as a demonstration reactor, Phenix should be able to provide additional information on this phenomenon, and one will see that we have been able to shed light on some points which the experiments or irradiations made to date have been unable to explain. However, before presenting the experimental results obtained with Phenix fuel end drawing conclusions, we shall give a brief resume of the expected behavior of this fuel with respect to the phenomenon of interest. (author)

  5. Alternative fuels for the French fast breeder reactors programme

    International Nuclear Information System (INIS)

    Bailly, H.; Bernard, H.; Mansard, B.

    1989-01-01

    French fast breeder reactors use mixed oxide as reference fuel. A great deal of experience has been gained in the behaviour and manufacture of oxide fuel, which has proved to be the most suitable fuel for future commercial breeder reactors. However, France is maintaining long-term alternative fuels programme, in order to be in a position to satisfy eventually new future reactor design and operational requirements. Initially, the CEA in France developed a carbide-based, sodium-bonded fuel designed for a high specific power. The new objective of the alternative fuels programme is to define a fuel which could replace the oxide without requiring any significant changes to the operating conditions, fuel cycle processes or facilities. The current program concentrates on a nitride-based, helium-bonded fuel, bearing in mind the carbide solution. The paper describes the main characteristics required, the manufacturing process as developed, the inspection methods, and the results obtained. Present indications are that the industrial manufacture of mixed nitride is feasible and that production costs for nitride and oxide fuels would be not significantly different. (author) 8 refs., 2 figs

  6. Heavy ion collisions at collider energies – Insights from PHENIX

    Indian Academy of Sciences (India)

    44KFKI Research Institute for Particle and Nuclear Physics (RMKI), Budapest, Hungary†. 1. Introduction. PHENIX is one of the five experiments at the recently commissioned RHIC collider at. Brookhaven National Laboratory. During the year 2000 first data with gold beams were taken at a center-of-mass energy of 130 GeV.

  7. Status of fast reactors and ADS programmes in France in 2000

    International Nuclear Information System (INIS)

    Astegiano, J.C.; Tailland, C.; Grenet, P.; Frith, R.; Fiorini, J.L.; Louvet, J.

    2001-01-01

    Two of the 4 N4 units (Chooz B1 et 2) were declared to be in commercial operation during 2000. The EDF owns 58 PWRs, for a total capacity of 63 GWe. The availability factor was 80.8 %, the new N4s run well. No particular incident occurred, 469 incidents were declared, 134 of which were rated 'level 1' and 2 incidents, 'level 2'. These incidents were often attributed to human factors originally and lasting generic problems. France, thanks to its large infrastructure of existing nuclear power stations which provides it with cheap energy, also finds itself in a strong position in the battle against 'The Greenhouse Effect'. The General Administrator of the CEA, Mr. Pascal Colombani, has called for a general restructuration of the nuclear industry in order to meet the challenges of deregulation and globalisation. The French Government has confirmed a process due to be completed in autumn of this year. Two main conclusions emerge dealing with the Long-Term Options for a French energy policy: Existing nuclear plants should retain their cost advantage over combined-cycle gas plants - the only serious economic challenge in terms of meeting the bulk of future electricity demand; Unless gas prices remain stable over the period as a whole, nuclear energy is also likely to retain its economic edge when the time comes to build new generating capacity. Renovation and inspection works have been actively pursued on the PHENIX plant, a large part of the work has been completed, mainly reinforcement against earthquakes, inspection of the internal structures and general maintenance. Maintenance work revealed cracks in the SGU and it has been decided to replace the potentially affected zones of SGU 1 and 3. Decommissioning work is underway at SUPERPHENIX, core unloading has proceeded normally, an increasing number of systems and components have been removed from service. A new decree will have to be issued for the final disposal of both the primary and secondary sodium; it will include

  8. R and D program for French sodium fast reactor: On the description and detection of sodium boiling phenomena during sub-assembly blockages

    International Nuclear Information System (INIS)

    Vanderhaegen, M.; Paumel, K.; Seiler, J. M.; Tourin, A.; Jeannot, J. P.; Rodriguez, G.

    2011-01-01

    In support of the French ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) reactor program, which aims to demonstrate the industrial applicability of sodium fast reactors with an increased level of safety demonstration and availability compared to the past French sodium fast reactors, emphasis is placed on reactor instrumentation. It is in this framework that CEA studies continuous core monitoring to detect as early as possible the onset of sodium boiling. Such a detection system is of particular interest due to the rapid progress and the consequences of a Total Instantaneous Blockage (TIB) at a subassembly inlet, where sodium boiling intervenes in an early phase. In this paper, the authors describe all the particularities which intervene during the different boiling stages and explore possibilities for their detection. (authors)

  9. PHENIX CDR update: An experiment to be performed at the Brookhaven National Laboratory relativistic heavy ion collider. Revision

    International Nuclear Information System (INIS)

    1994-11-01

    The PHENIX Conceptual Design Report Update (CDR Update) is intended for use together with the Conceptual Design Report (CDR). The CDR Update is a companion document to the CDR, and it describes the collaboration's progress since the CDR was submitted in January 1993. Therefore, this document concentrates on changes, refinements, and decisions that have been made over the past year. These documents together define the baseline PHENIX detector that the collaboration intends to build for operation at RHIC startup. In this chapter the current status of the detector and its motivation are briefly described. In Chapters 2 and 3 the detector and the physics performance are more fully developed. In Chapters 4 through 13 the details of the present design status, the technology choices, and the construction costs and schedules are presented. The physics goals of PHENIX collaboration have remained exactly as they were described in the CDR. Primary among these is the detection of a new phase of matter, the quark-gluon plasma (QGP), and the measurement of its properties. The PHENIX experiment will measure many of the best potential QGP signatures to see if any or all of these physics variables show anomalies simultaneously due to the formation of the QGP

  10. Acoustic sodium-water reaction detection of the Phenix steam generators

    International Nuclear Information System (INIS)

    Carminati, M.; Martin, L.; Sauzaret, A.

    1990-01-01

    The systems for acoustic sodium-water reaction detection and hydrogen detection of the Phenix steam generators as well as systems for monitoring signals analysis and processing are described. It is reported that the results obtained during operation and calibration phases are very encouraging and that industrial equipment showing the same performance are being examined. 6 figs

  11. Accurate macromolecular crystallographic refinement: incorporation of the linear scaling, semiempirical quantum-mechanics program DivCon into the PHENIX refinement package

    Energy Technology Data Exchange (ETDEWEB)

    Borbulevych, Oleg Y.; Plumley, Joshua A.; Martin, Roger I. [QuantumBio Inc., 2790 West College Avenue, State College, PA 16801 (United States); Merz, Kenneth M. Jr [University of Florida, Gainesville, Florida (United States); Westerhoff, Lance M., E-mail: lance@quantumbioinc.com [QuantumBio Inc., 2790 West College Avenue, State College, PA 16801 (United States)

    2014-05-01

    Semiempirical quantum-chemical X-ray macromolecular refinement using the program DivCon integrated with PHENIX is described. Macromolecular crystallographic refinement relies on sometimes dubious stereochemical restraints and rudimentary energy functionals to ensure the correct geometry of the model of the macromolecule and any covalently bound ligand(s). The ligand stereochemical restraint file (CIF) requires a priori understanding of the ligand geometry within the active site, and creation of the CIF is often an error-prone process owing to the great variety of potential ligand chemistry and structure. Stereochemical restraints have been replaced with more robust functionals through the integration of the linear-scaling, semiempirical quantum-mechanics (SE-QM) program DivCon with the PHENIX X-ray refinement engine. The PHENIX/DivCon package has been thoroughly validated on a population of 50 protein–ligand Protein Data Bank (PDB) structures with a range of resolutions and chemistry. The PDB structures used for the validation were originally refined utilizing various refinement packages and were published within the past five years. PHENIX/DivCon does not utilize CIF(s), link restraints and other parameters for refinement and hence it does not make as many a priori assumptions about the model. Across the entire population, the method results in reasonable ligand geometries and low ligand strains, even when the original refinement exhibited difficulties, indicating that PHENIX/DivCon is applicable to both single-structure and high-throughput crystallography.

  12. The French experience concerning the contamination by inactive and radioactive impurities and the purification of the cover gas of LMFBRs

    Energy Technology Data Exchange (ETDEWEB)

    Michaille, P [CEA/IRDI/DEDR/DRNR/STRA, C.E.N. Cadarache (France); Clerc, R [CEA/IRDI/DERPE/SCPx, C.E.N. Marcoule (France); comps.

    1987-07-01

    With regard to the problems related to the cover gas of LMFBRs, the French position based on the experience of RAPSODIE and PHENIX can be summarized as follows: 1. No particular difficulty has been encountered with impurities such as air. The consequences of lubricants leaks were limited to the maintenance of big components. 2. Concerning the contamination by radioactive species, the main source in the reactor tank is {sup 23}Ne, but fortunately its half decay period is very short (38 s). Two managements of fuel failures were experienced. On RAPSODIE, the failures were numerous for experimental purpose and - in the absence of an efficient localization device - often simultaneous. On PHENIX, the fuel failure rate appears to be very low. Furthermore, the gas analysis unit of the fuel failure localization device (LRG/gas) has been improved steadily, which permits to localize and follow the evolution of each individual failed sub-assembly from the very beginning of the clad failure. For both of the reactors, leaks through the roof were observed, for which solutions were found. 3. The analysis equipment of RAPSODIE and PHENIX evolved to account for: the needs of the operator; experimental programs. The experience gained permitted to select for SUPER PHENIX a simple instrumentation. 4. Limited efforts have been paid to the purification techniques towards the fission products: On RAPSODIE, the use of helium as cover gas allowed to use trapping with charcoal cooled with liquid nitrogen with a high efficiency not only towards xenons, but also kryptons. On PHENIX, it is not necessary to trap krypton: the release rates of {sup 85}Kr (T1/2=10,4 a) are very low, of the same order as {sup 37}Ar (T1/2=35 d) produced by activation, and the fuel failure localization is not performed by gas tagging. Therefore, cooled charcoal adsorption is sufficient. For experimental purpose, a cryogenic distillation column has been installed at PHENIX, but has not yet been put into operation

  13. EDF research on fast neutron reactors

    International Nuclear Information System (INIS)

    In order to make possible the calculation of the temperatures of the sodium, of the sheath and of the fuel in fast reactor assemblies, taking into account the mixing phenomena induced by the helicoidal wires, two design codes have been developed. Those codes have then been adapted for their integration in the Superalcyon system. This system shall constitute the reference tool for the development of those codes that shall manage Phenix, and other reactors of the family. Cooling accidents, thermohydraulic studies, and steam generator studies are also in progress

  14. Balance and behavior of gaseous radionuclides released during initial fast reactor fuel reprocessing operations

    International Nuclear Information System (INIS)

    Leudet, A.; Goumondy, J.P.; Charrier, G.

    1985-10-01

    Five pins from the fast reactor Phenix are cut and dissolved in a specially designed cell for the accurate determination of gas released during the operation. Amount and activity of gaseous radionuclides: Kr, Xe, Kr-85, I, I-129, H-3 and C-14 are determined in the fuel pins and also their distribution between shearing and dissolution [fr

  15. Safety requirements and options for a large size fast neutron reactor

    International Nuclear Information System (INIS)

    Cogne, F.; Megy, J.; Robert, E.; Benmergui, A.; Villeneuve, J.

    1977-01-01

    Starting from the experience gained in the safety evaluation of the PHENIX reactor, and from results already obtained in the safety studies on fast neutron reactors, the French regulatory bodies have defined since 1973 what could be the requirements and the recommendations in the matter of safety for the first large size ''prototype'' fast neutron power plant of 1200 MWe. Those requirements and recommendations, while not being compulsory due to the evolution of this type of reactors, will be used as a basis for the technical regulation that will be established in France in this field. They define particularly the care to be taken in the following areas which are essential for safety: the protection systems, the primary coolant system, the prevention of accidents at the core level, the measures to be taken with regard to the whole core accident and to the containment, the protection against sodium fires, and the design as a function of external aggressions. In applying these recommendations, the CREYS-MALVILLE plant designers have tried to achieve redundancy in the safety related systems and have justified the safety of the design with regard to the various involved phenomena. In particular, the extensive research made at the levels of the fuel and of the core instrumentation makes it possible to achieve the best defence to avoid the development of core accidents. The overall examination of the measures taken, from the standpoint of prevention and surveyance as well as from the standpoint of means of action led the French regulatory bodies to propose the construction permit of the CREYS MALVILLE plant, provided that additional examinations by the regulatory bodies be made during the construction of the plant on some technological aspects not fully clarified at the authorization time. The conservatism of the corresponding requirements should be demonstrated prior to the commissioning of the power plant. To pursue a programme on reactors of this type, or even more

  16. French approach in fuel pin modelling for fast reactors

    Energy Technology Data Exchange (ETDEWEB)

    Pascard, R [CEA-Centre de Fontenay-aux-Roses, Fontenay-aux-Roses (France)

    1979-12-01

    The purpose of this paper is to present the general philosophy on the problem of fuel modelling now prevailing in France after a twelve years period of tremendously increasing knowledge on fuel behavior. When the Rapsodie fuel pin was designed in 1962 , little was known about the behavior of a mixed oxide fuel pin under fast flux ; but a large body of knowledge on UO{sub 2} behavior in thermal reactor was available together with some sparse irradiation results on (U Pu)O{sub 2} in French experimental reactors. The performances assigned to the pin were then rather modest in rating (400 w/cm) and in burnup (30,000 MWd/t). The AISI 316 steel in solution annealed state was chosen as cladding material. The clad itself was supposed to deform by thermal creep due to fission gas pressure (100% release), and was affected consequently by a strain limit criteria. The importance of clad temperature ({approx}650 deg.) was considered only in connection with thermal creep, the possibility of a chemical reaction between mixed oxide and clad being at that time hardly suspected. Rapsodie had only been at full power for a few months when appeared the evidence of stainless steel swelling under a fast neutrons flux. This swelling was observed on Rapsodie pins as soon as they experienced sufficient neutrons dose, roughly one year later. This entirely new problem came immediately in the front stage (and is still of major importance today), and was at the origin of the change from the Rapsodie to the Fortissimo core in order to accelerate materials testing versus void swelling by multiplying the flux by a factor two. Even with unforeseen swelling, the design of the Rapsodie and later on Fortissimo pin, allowed not only to reach the goal burnup, but to increase it steadily to roughly 100,000 MWd/t. Since then, the French approach in fuel pin design has still retained something of its original simplicity, and technological efficiency, attitude which is justified by the following

  17. 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

  18. 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

  19. First measurement of J/ψ azimuthal anisotropy in PHENIX at forward rapidity in Au+Au collisions at √(sNN) = 200 GeV

    International Nuclear Information System (INIS)

    Silvestre, Catherine

    2009-01-01

    The PHENIX experiment has shown that J/ψ s are suppressed in central Au+Au collisions at a center of mass energy per nucleon-nucleon collision √(s NN ) = 200 GeV, and that the suppression is larger at forward than at mid-rapidity. Part of this difference may be explained by cold nuclear matter effects but the most central collisions suggest that regeneration mechanisms could be at play. In 2007, PHENIX collected almost four times more Au+Au collisions at this energy than used for previous published results. Moreover, the addition of a new reaction plane detector allows a much better analysis of the J/ψ behavior in the azimuthal plane. Since a large elliptic flow has been measured for open charm, measuring J/ψ azimuthal anisotropies may give a hint if J/ψ are recombined in the expanding matter. First PHENIX results of J/ψ elliptic flow as a function of transverse momentum at forward rapidity are presented in this article. The analysis is detailed and results are compared to mid-rapidity PHENIX preliminary results as well as to predictions. (orig.)

  20. Data processing and data collection in Super-Phenix

    International Nuclear Information System (INIS)

    Josue, M.; Thegner, G.

    1978-01-01

    The data processing systems for the Super-Phenix power station have been developed from Phenix systems, the various tasks being specified on the basis of the origin of information (specific to the boiler or common to the whole power station) and of its nature, i.e. depending on whether it is used for protection or for operational purposes or whether it provides personnel with a better understanding of phenomena related to the reactor. The data processing systems specific to the boiler are as follows: (a) the core temperature processing system (TRTC) with which fuel assembly temperatures can be monitored and any abnormally high value discovered, in which case it can cause a trip to shut down the reactor. To this extent it can be seen as part of the station safety equipment. In the interest of channel separation and satisfactory availability, the system is made up of two identical units based on the use of mini-computers, some of which (for analog acquisition) are decentralized and placed near the measuring points in the dome; and (b) the core fault detection and diagnosis system (DDDC), which is a necessary complement to the TRTC in that it fulfils certain boiler operation tasks and supplies information if incidents occur. It is made up of three subsystems (acquisition and retrieval, reactivity comparison, noise analysis). Among the systems applicable to the overall operation of the station, there is: (c) the complementary information processing system (TCI) which provides overall control and is based on a large quantity of information connected with the facility as a whole. (author)

  1. The most prominent safety guarantees

    International Nuclear Information System (INIS)

    Lucenet, G.

    1978-01-01

    The Creys-Malville Nuclear Centre has been designed using the safety analysis implemented since the beginning of the developments of breeder reactors in France and the Super Phenix follows almost the same safety regulations as its predecessor the Phenix reactor. These regulations are based on: 'Recommendations for the safety standards of the Super Phenix' drawn up by the French Safety Authorities in July 1973. The prominent points are summarised. (C.F.)

  2. Modelling of an ULOF transient in a sodium fast reactor

    International Nuclear Information System (INIS)

    Droin, Jean-Baptiste

    2016-01-01

    Within the framework of the Generation IV Sodium-cooled Fast Reactor (SFR) R and D program of CEA (French Commissariat a l'Energie Atomique et aux Energies Alternatives), safety in case of severe accidents is assessed.Such transients are usually simulated with mechanistic codes (such as SAS-SFR and SIMMER III). as a complement to these codes, which give reference accidental transient calculations, a new physico-statistical approach is currently followed by the CEA; its final objective being to derive the variability of the main results of interest for safety. This approach involves a fast-running description of extended accident sequences coupling physical models for the main phenomena to advanced statistical analysis techniques. It enables to perform a large number of simulations in a reasonable computational time and to describe all the possible bifurcations of the accident transient.In this context, this PhD work presents the physical tool (models and results assessment) dedicated to the initiation and primary phases of an Unprotected Loss Of Flow accident (i.e. until the end of sub-assemblies degradation and before large molten pools formation). The accident phenomenology during these phases is described and illustrated by numerous experimental evidences.It is underlined that the features of the new heterogeneous core concept (called CFV of the French ASTRID prototype) leads to different kinds of ULOF transients than those occurring in the previous past homogeneous cores (SuperPhenix, Phenix...). Indeed, its negative void effect drops the nuclear power when sodium heats-up and possibly boils. This enables three types of ULOF transients characterized by various core final states; the first two types leading to final coolable core states in natural circulation flow (the first one in single phase, the second one in stabilized two-phase flow) whereas the core undergoes a flow excursion followed by sub-assemblies degradation in the last type. In this study, a

  3. PHENIX On-Line Distributed Computing System Architecture

    International Nuclear Information System (INIS)

    Desmond, Edmond; Haggerty, John; Kehayias, Hyon Joo; Purschke, Martin L.; Witzig, Chris; Kozlowski, Thomas

    1997-01-01

    PHENIX is one of the two large experiments at the Relativistic Heavy Ion Collider (RHIC) currently under construction at Brookhaven National Laboratory. The detector consists of 11 sub-detectors, that are further subdivided into 29 units (''granules'') that can be operated independently, which includes simultaneous data taking with independent data streams and independent triggers. The detector has 250,000 channels and is read out by front end modules, where the data is buffered in a pipeline while awaiting the level trigger decision. Zero suppression and calibration is done after the level accept in custom built data collection modules (DCMs) with DSPs before the data is sent to an event builder (design throughput of 2 Gb/sec) and higher level triggers. The On-line Computing Systems Group (ONCS) has two responsibilities. Firstly it is responsible for receiving the data from the event builder, routing it through a network of workstations to consumer processes and archiving it at a data rate of 20 MB/sec. Secondly it is also responsible for the overall configuration, control and operation of the detector and data acquisition chain, which comprises the software integration for several thousand custom built hardware modules. The software must furthermore support the independent operation of the above mentioned granules, which includes the coordination of processes that run in 60-100 VME processors and workstations. ONOS has adapted the Shlaer- Mellor Object Oriented Methodology for the design of the top layer software. CORBA is used as communication layer between the distributed objects, which are implemented as asynchronous finite state machines. We will give an overview of the PHENIX online system with the main focus on the system architecture, software components and integration tasks of the On-line Computing group ONCS and report on the status of the current prototypes

  4. Direct Photons and Dileptons in PHENIX at RHIC

    International Nuclear Information System (INIS)

    David, G.

    2009-01-01

    Direct photons and dileptons are penetrating probes of relativistic heavy ion collisions. Generated throughout the entire history of the collision and then emerging without further interaction they give insight into basic processes that are otherwise not directly accessible experimentally. One of the main objectives and strengths of the PHENIX experiment at RHIC is the measurement of both types of electromagnetic probes in the same apparatus and in the widest p T range in nucleon-nucleon and heavy ion collisions. The experimental results and recent developments of theory started to change our perception of high transverse momentum photons from A+A collisions.

  5. Manufacture of the first fuel charge for the SUPER-PHENIX 1 reactor

    International Nuclear Information System (INIS)

    Pajot, J.; Beche, M.; Heyraud, J.

    1988-01-01

    After summarizing same general points on the Super Phenix core, the performances of fuel essemblies, the remainder of this discussion will deal with the manufacture by the CFCa of the first charge of fuel assemblies. The following aspects are considered in sequence - contract - production facilities - manufacturing procedures finally a few assessments will be presented

  6. Operating experience of RAPSODIE and PHENIX relating to sodium aerosols and vapours

    Energy Technology Data Exchange (ETDEWEB)

    Delisle, J P; Reboul, M; Elie, X [DRNR/STRS - Centre de Cadarache, Saint-Paul-lez-Durance (France)

    1977-01-01

    The main difficulties resulting from sodium aerosols and vapours in the cover gas which have been encountered for 10 years in RAPSODIE and for 3 years in PHENIX are reviewed: condensation of sodium in annular spaces; plugging in primary gas pipes; plugging of filters and vapour traps. All those problems were easily overcome. (author)

  7. ϕ Meson Production at Forward Rapidity with the PHENIX Detector at RHIC

    Science.gov (United States)

    Sarsour, Murad

    2017-12-01

    The ϕ meson production in p+p collisions is an important tool to study QCD, providing data to tune phenomenological QCD models, while in high-energy heavy-ion collisions it provides key information on the hot and dense state of the strongly interacting matter produced in such collisions. It is sensitive to the medium-induced effects such as strangeness enhancement, a phenomenon associated with soft particles in bulk matter. Measurements in the dilepton channels are especially interesting since leptons interact only electromagnetically, thus carrying the information from their production phase directly to the detector. Measurements in different nucleus-nucleus collisions allow us to perform a systematic study of the nuclear medium effects on ϕ meson production. The PHENIX detector provides the capabilities to measure the ϕ meson production in a wide range of transverse momentum and rapidity to study various cold nuclear effects such as soft multiple parton rescattering and modification of the parton distribution functions in nuclei. In this proceeding, we report the most recent PHENIX results on ϕ meson production in p+p, d+Au and Cu+Au collisions.

  8. Accurate macromolecular crystallographic refinement: incorporation of the linear scaling, semiempirical quantum-mechanics program DivCon into the PHENIX refinement package.

    Science.gov (United States)

    Borbulevych, Oleg Y; Plumley, Joshua A; Martin, Roger I; Merz, Kenneth M; Westerhoff, Lance M

    2014-05-01

    Macromolecular crystallographic refinement relies on sometimes dubious stereochemical restraints and rudimentary energy functionals to ensure the correct geometry of the model of the macromolecule and any covalently bound ligand(s). The ligand stereochemical restraint file (CIF) requires a priori understanding of the ligand geometry within the active site, and creation of the CIF is often an error-prone process owing to the great variety of potential ligand chemistry and structure. Stereochemical restraints have been replaced with more robust functionals through the integration of the linear-scaling, semiempirical quantum-mechanics (SE-QM) program DivCon with the PHENIX X-ray refinement engine. The PHENIX/DivCon package has been thoroughly validated on a population of 50 protein-ligand Protein Data Bank (PDB) structures with a range of resolutions and chemistry. The PDB structures used for the validation were originally refined utilizing various refinement packages and were published within the past five years. PHENIX/DivCon does not utilize CIF(s), link restraints and other parameters for refinement and hence it does not make as many a priori assumptions about the model. Across the entire population, the method results in reasonable ligand geometries and low ligand strains, even when the original refinement exhibited difficulties, indicating that PHENIX/DivCon is applicable to both single-structure and high-throughput crystallography.

  9. Characteristics and behaviour of the PHENIX fuel element

    International Nuclear Information System (INIS)

    Delpeyroux, P.; Balloffet, Y.; Blanchard, P.; Courcon, P.; Jallade, M.; Millet, P.; Rousseau, J.; Carteret, Y.; Coulon, P.

    1977-01-01

    The Phenix reactor has been in regular industrial operation for two years and has functioned very satisfactorily thanks in particular to the very good behaviour of the fuel element. A brief description is given of the fuel element and the operating conditions which were set for the fuel at the time of start-up (50000 MWd/t). The surveillance scheme is then described with the examinations in the hot laboratory on the basis of which it was possible to achieve the nominal specific burn-up and then to clear the Phenix fuel for a specific burn-up of 60000 MWd/t or 7 at.%. The behaviour of the mixed oxide (U, Pu)O 2 is quite normal and conforms to predictions as regards the heat conditions, swelling and fission gas release. The corrosion reaction between the oxide and the clad is progressing slowly and affects only small thicknesses of cladding. The mechanical integrity of the clad under thermal stresses and the stresses produced by swelling and fission gas pressure do not pose any special problem. The present limitation of the irradiation level is essentially based on the permissible deformations due to swelling and irradiation creep in the fuel pin cladding and in the hexagonal tube. This corresponds to damage to the steel of the order of 80 dpa. The mechanical behaviour of the bundle of pins, its interaction with the hexagonal tube and the thermohydraulic consequences of the deformations are all satisfactory to date. The absence of fuel failures is also worth noting; the only burst can detected to date did not affect either the operation of the fuel assembly or the performance of the reactor [fr

  10. The dynamic behavior of the SUPER-PHENIX reactor under unprotected transient

    International Nuclear Information System (INIS)

    Gouriou, A.; Francillon, E.; Kayser, G.; Malenfer, G.; Languille, A.

    1982-01-01

    Due to design changes and progress on the knowledge of feed-back effects, a reactualization of the dynamic behavior of SUPER-PHENIX under unprotected transients was undertaken. We present the main data on feed-back characteristics and the results of dynamic calculations. With the present state of knowledge, the former conclusion is confirmed: the dynamic evolution is very slow and no irreversible phenomena happen in the short term

  11. Some aspects of sodium technology issued from the operating experience of RAPSODIE and PHENIX

    International Nuclear Information System (INIS)

    Kremser, J.; Lacroix, A.

    1976-01-01

    This paper deals with the experience on sodium technology gained from RAPSODIE and PHENIX operation. Problems encountered with sodium circuits, main components, handling equipment and instrumentation are discussed. Some information related to the contamination by radioactive products of sodium and sodium circuits is given

  12. PHENIX results on open heavy flavor production

    Science.gov (United States)

    Hachiya, Takashi

    2018-02-01

    PHENIX measures the open heavy flavor productions in p + p, Cu+Au, and Au+Au collisions at = 200 and 510 GeV using the silicon tracking detectors for mid- and forward rapidities. In Au+Au collisions, the nuclear modification of single electrons from bottom and charm hadron decays are measured for minimum bias and most central collisions. It is found that bottoms are less suppressed than charms in pT=3-5 GeV/c and charms in most central collisions are more suppressed than that in minimum bias collisions. In p + p and Cu+Au collisions, J/ψ from B meson decays are measured at forward and backward rapidities. The nuclear modification of B mesons in Cu+Au collisions is consistent with unity.

  13. Utilisation and performance of sodium instrumentation during start-up and initial operation of Phenix

    International Nuclear Information System (INIS)

    Lions, N.; Buis, H.; Baron, J.; Fournier, C.; Gourdon, J.

    1976-01-01

    The main process-instruments on the Phenix reactor are presented with the exception of the FFDL System and of the hydrogen-detector which are described in other papers. The results obtained during reactor start-up and during initial operation of the nuclear power-station are given [fr

  14. The treatment of absorber rod heterogeneity effects using homogeneous equivalent cross-sections and their application in large fast reactors

    International Nuclear Information System (INIS)

    Newton, T.D.

    1988-01-01

    This paper examines the application of homogeneous equivalent absorber rod cross-sections to the calculation of control rod anti-reactivities in large fast reactors. The method used to obtain the equivalent cross-sections is described and their validity in simple whole core geometry calculations is verified. Finally, they are employed in the calculation of control rod anti-reactivity worths in the Super Phenix 1 fast reactor and the results are compared with measured values. (author). 5 refs, 5 figs, 9 tabs

  15. Oxide fuels and targets for transmutation

    International Nuclear Information System (INIS)

    Sudreau, F.; Bonnerot, J.M.; Warin, D.; Gaillard-Groleas, G.; Ferroud-Plattet, M.P.

    2007-01-01

    Full text of publication follows. Direction 1 of the French Act dated 30 December 1991 on the management of high-level, long-lived radioactive waste involves exploring solutions designed to separate long-lived radionuclides from the spent fuel and to transmute them under neutron flux into shorter half-lives or stable elements. In the French research programme conducted by CEA, these radionuclides are mainly minor actinides (americium, neptunium and curium) and fission products (particularly caesium, iodine and technetium). Within this context, this paper aims at illustrating the vast programme that CEA has performed in order to demonstrate the scientific and technical feasibility of minor actinide transmutation. An important part of the research was carried out in collaboration with French research (CNRS) and industrial (EDF, AREVA) organisations, and also in the framework of international co-operation programmes with the European Institute for Transuranium Elements in Karlsruhe (ITU), the US Department of Energy (DOE), the Japanese Atomic Energy Research Institute (now JAEA) and Central Research Institute of Electric Power Industry (CRIEPI) and the Russian Ministry for Atomic Energy (ROSATOM). Such research made it possible to evaluate the capacity of MOX fuels to be used as a support for minor actinide transmutation (homogeneous method). Simulations of pressurised water reactor (PWR) fuels have revealed the limits of this transmutation method, which are mainly related to the pressurization of the fuel rods and the formation of high active californium. On the contrary, for sodium-cooled fast reactor fuels possibly designed with large expansion plenums a first experimental demonstration of the transmutation of americium and neptunium has been successful in the Phenix reactor. Various studies designed to demonstrate the theoretical and experimental feasibility of transmutation using an inert support (heterogeneous method) have been carried out in HFR (EFTTRA

  16. First measurement of J/{psi} azimuthal anisotropy in PHENIX at forward rapidity in Au+Au collisions at {radical}(s{sub NN}) = 200 GeV

    Energy Technology Data Exchange (ETDEWEB)

    Silvestre, Catherine [CEA-Saclay, IRFU, Gif-sur-Yvette (France)

    2009-06-15

    The PHENIX experiment has shown that J/{psi} s are suppressed in central Au+Au collisions at a center of mass energy per nucleon-nucleon collision {radical}(s{sub NN}) = 200 GeV, and that the suppression is larger at forward than at mid-rapidity. Part of this difference may be explained by cold nuclear matter effects but the most central collisions suggest that regeneration mechanisms could be at play. In 2007, PHENIX collected almost four times more Au+Au collisions at this energy than used for previous published results. Moreover, the addition of a new reaction plane detector allows a much better analysis of the J/{psi} behavior in the azimuthal plane. Since a large elliptic flow has been measured for open charm, measuring J/{psi} azimuthal anisotropies may give a hint if J/{psi} are recombined in the expanding matter. First PHENIX results of J/{psi} elliptic flow as a function of transverse momentum at forward rapidity are presented in this article. The analysis is detailed and results are compared to mid-rapidity PHENIX preliminary results as well as to predictions. (orig.)

  17. Common lessons drawn from different laboratories analyses of super-phenix start-up experiments

    International Nuclear Information System (INIS)

    Cabrillat, J.C.; Salvatores, M.; Carta, M.; D'Angelo, A.; Giese, H.; De Wouters, R.; Newton, T.; Harrison, P.; Sztark, H.; Wehmann, U.

    1990-01-01

    Measurements issued from the SUPER-PHENIX start-up experiments have been analysed by the different partners within the European Community with their own data and methods. Common lessons can be drawn from the different analyses and recommendations made on the definition of the characteristics of a common European formulaire and in the actions in support of its qualification

  18. Reconstructed Jet Results in p + p, d + Au and Cu + Cu collisions at 200 GeV from PHENIX

    International Nuclear Information System (INIS)

    Perepelitsa, D.V.

    2013-01-01

    Jet reconstruction in heavy ion collisions at RHIC and the LHC is becoming a popular tool to explore medium effects including the energy loss and modified fragmentation of hard-scattered partons. In p + A and d + A collisions, reconstructed jets are important for evaluating cold nuclear matter effects such as the impact parameter dependence of nuclear parton distribution functions and initial state energy loss. We present current PHENIX results from p + p, d + Au, and Cu + Cu collisions at 200 GeV using the Gaussian filter and anti-k T algorithms. The systematic study of direct jet reconstruction across a variety of collisions systems at PHENIX will help to tell a coherent story of jet physics at RHIC

  19. The yawning chasm of French nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    This is an account of a paper appeared in Energy Economist, February 1988 and contains a severe critique of the French nuclear power policy, in particular the Electricite de France, Cogema and Framatome. It is argued that the blueprint of the original nuclear power program has not been achieved in many topics. Points of critique to the EdF are: the electricity price, overcapacities and financial indeptedness. The French industries are not flourishing due to ample supply of cheap energy, nor do French nuclear manufacturers sell the fast breeder technology throughout the world. (qui)

  20. Synthesis method validation for Super-Phenix 1 start-up core studies

    International Nuclear Information System (INIS)

    Pipaud, J.Y.; Gastaldo, G.; Giacometti, C.

    1980-09-01

    This paper aims at presenting the systematic studies performed in order to check and to improve the synthesis method wich is used to optimize the configuration of the SUPER-PHENIX 1 start-up core versus the diluent subassembly location and the control rod ring insertion. A special attention is paid to the choice of the trial functions when the two rod rings have different insertion depths. Present limits of the synthesis method are given and further improvements are indicated

  1. Integral measurement of fission products capture in fast breeder reactors

    International Nuclear Information System (INIS)

    Martin Deidier, Loick.

    1979-12-01

    For the SUPERPHENIX reactor project, it was necessary to know fission products capture with about 10% accuracy in the fast breeder reactor spectra. In this purpose, integral measurements have been carried out on the main separated products by different experimental technics (oscillation, activation and irradiation methods), but particularly on irradiated fuel pins from RAPSODIE and PHENIX reactors in order to directly obtain total effect of fission products. Same tendencies have been observed for both enriched uranium fuel and LMFBR characteristic plutonium fuel. All experimental results have been introduced in CARNAVAL cross section set [fr

  2. Problems specific to the piping of sodium-cooled fast breeder reactors

    International Nuclear Information System (INIS)

    Vrillon, B.; Befre, J.; Schaller, K.

    1975-01-01

    A certain number of specific problems arising in connection with the sodium pipes in fast neutron reactors, especially those of large diameter, are presented. The supporting system must be designed to achieve the best compromise among stresses due to weight and various stresses of thermal origin. Large-scale experimental studies carried out on actual elements of the intermediate circuit of the Phenix reactor showed that the circuits can withstand considerable deformation collapse of the walls without danger of leakage. Protection studies against earthquakes are mentionned [fr

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

    International Nuclear Information System (INIS)

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

    1991-11-01

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

  4. Development of fast reactor metal fuels containing minor actinides

    International Nuclear Information System (INIS)

    Ohta, Hirokazu; Ogata, Takanari; Kurata, Masaki; Koyama, Tadafumi; Papaioannou, Dimitrios; Glatz, Jean-Paul; Rondinella, Vincenzo V.

    2011-01-01

    Fast reactor metal fuels containing minor actinides (MAs) Np, Am, and Cm and rare earths (REs) Y, Nd, Ce, and Gd are being developed by the Central Research Institute of Electric Power Industry (CRIEPI) in collaboration with the Institute for Transuranium Elements (ITU) in the METAPHIX project. The basic properties of U-Pu-Zr alloys containing MA (and RE) were characterized by performing ex-reactor experiments. On the basis of the results, test fuel pins including U-Pu-Zr-MA(-RE) alloy ingots in parts of the fuel stack were fabricated and irradiated up to a maximum burnup of ∼10 at% in the Phenix fast reactor (France). Nondestructive postirradiation tests confirmed that no significant damage to the fuel pins occurred. At present, detailed destructive postirradiation examinations are being carried out at ITU. (author)

  5. Measurement of Double Longitudinal Spin Asymmetry, ALL, for Inclusive 0̂ Production at Forward Rapidity in PHENIX for √s=200 and 500 GeV

    Science.gov (United States)

    Wolin, Scott

    2010-11-01

    The Relativistic Heavy Ion Collider (RHIC) is the world's only source of polarized proton-proton collisions which provides access at leading order to δ G(x), the gluon contribution to the proton spin. Previously, PHENIX has only been sensitive to truncated moments of δ G over the limited Bjorken-x range of 0.05 Piston Calorimeter (MPC) at forward rapidity, di-hadron measurements with hadrons at both forward and central rapidities are now possible in PHENIX. Two forward hadrons extend the kinematic coverage for gluons down to x˜10-3. Such an asymmetry measurement for di-hadrons and single hadrons at forward rapidity can be used to improve the constraints on δ G(x) at small x. Here, we discuss the status of these measurements at forward rapidity in PHENIX using the MPC.

  6. French experience concerning expansion compensating devices on the primary systems of nuclear reactors

    International Nuclear Information System (INIS)

    Vrillon, B.; Raynal, A.

    1980-01-01

    French experience in the use of large expansion bellows in the presence of hot sodium is extremely limited. This stems from the 'pool' structure of the primary circuit, adopted in France to eliminate the need to solve expansion problems affecting the primary piping of loop reactors. Furthermore, until the present time, the use of bellows on secondary circuits has neither been implemented nor considered. A few bellows nevertheless exist on the Phenix and Super-Phenix reactors, and these perform separation functions, for example, between sodium at different temperature and/or pressures, or tightness functions in gaseous environment at the component penetrations in the slabs. The dimension criteria applied to these bellows are the general rules for structural dimensioning. Since they do not form part of a circuit wall, they do not need to be discussed. Note, however, that these components have not raised any particular problems thus far. Expansion bellows exist in France on the primary circuits of certain nuclear reactors of the natural uranium/graphite/gas type. These reactors have been in operation for many years, and some lessons can be drawn from this experience in the use of bellows in representative conditions on power reactor circuits. Liquid sodium raises specific problems with respect to circuit operation and material behavior. However, many problems in the use of bellows are independent of the fluid conveyed in the circuits. This is why the experience gained with gas type power reactors appears to be useful in considering the possible future use of bellows on sodium reactor circuits

  7. Performance of Front-End Readout System for PHENIX RICH

    International Nuclear Information System (INIS)

    Oyama, K.; Hamagaki, H.; Nishimura, S.; Shigaki, K.; Hayano, R.S.; Hibino, M.; Kametani, S.; Kikuchi, J.; Matsumoto, T.; Sakaguchi, T.; Ebisu, K.; Hara, H.; Tanaka, Y.; Ushiroda, T.; Moscone, C.G.; Wintenberg, A.L.; Young, G.R.

    1999-01-01

    A front-end electronics system has been developed for the Ring Imaging Cerenkov (RICH) detector of the PHENIX experiment at the Relativistic Heavy Ion Collider (RHIC), Brookhaven National Laboratory (BNL). A high speed custom back-plane with source synchronous bus architecture, a full custom analog ASIC, and board modules with FPGA's and CPLD's were developed for high performance real time data acquisition. The transfer rate of the back-lane has reached 640 MB/s with 128 bits data bus. Total transaction time is estimated to be less than 30 micros per event. The design specifications and test results of the system are presented in this paper

  8. Five years of operating experience with Phenix

    International Nuclear Information System (INIS)

    Conte, F.

    1980-01-01

    The construction of Phenix began at the end of 1968; the unit first went critical on August 31 st, 1973, and it was first connected to the grid of Electricite de France on 31st December 1973. It started operating industrially on July 14th, 1974. The balance sheet after five years of operations is as follows: Gross thermal capacity: 590 MW; Grosss electric capacity: 264 MW; Gross capacity factor of the power station: 45%; Gross electrical power produced by 30th september 1979: more than six billion kWh. In 1976 and 1977 the operation of the plant was affected by modifications made to the intermediate heat exchangers following leaks discovered in October 1976. Since 1976 the plants has been working at full capacity and the availability rate during the period July 1978 - July 1979 was more than 80% [fr

  9. PROPOSAL FOR A SILICON VERTEX TRACKER (VTX) FOR THE PHENIX EXPERIMENT.

    Energy Technology Data Exchange (ETDEWEB)

    AKIBA,Y.

    2004-03-30

    We propose the construction of a Silicon Vertex Tracker (VTX) for the PHENIX experiment at RHIC. The VTX will substantially enhance the physics capabilities of the PHENIX central arm spectrometers. Our prime motivation is to provide precision measurements of heavy-quark production (charm and beauty) in A+A, p(d)+A, and polarized p+p collisions. These are key measurements for the future RHIC program, both for the heavy ion program as it moves from the discovery phase towards detailed investigation of the properties of the dense nuclear medium created in heavy ion collisions, and for the exploration of the nucleon spin-structure functions. In addition, the VTX will also considerably improve other measurements with PHENIX. The main physics topics addressed by the VTX are: (1) Hot and dense strongly interacting matter--Potential enhancement of charm production; Open beauty production; Flavor dependence of jet quenching and QCD energy loss; Accurate charm reference for quarkonium; Thermal dilepton radiation; High p{sub T} phenomena with light flavors above 10-15 GeV/c in p{sub T}; and Upsilon spectroscopy in the e{sup +}e{sup -} decay channel. (2) Gluon spin structure of the nucleon--{Delta}G/G with charm; {Delta}G/G with beauty; and x dependence of {Delta}G/G with {gamma}-jet correlations. (3) Nucleon structure in nuclei--Gluon shadowing over broad x-range. With the present PHENIX detector, heavy-quark production has been measured indirectly through the observation of single electrons. These measurements are inherently limited in accuracy by systematic uncertainties resulting from the large electron background from Dalitz decays and photon conversions. In particular, the statistical nature of the analysis does not allow for a model-independent separation of the charm and beauty contributions. The VTX detector will provide vertex tracking with a resolution of <50 {micro}m over a large coverage both in rapidity (|{eta}| < 1.2) and in azimuthal angle ({Delta}{phi} {approx

  10. Sodium fire studies in France. Safety experiments applied to fast reactors

    International Nuclear Information System (INIS)

    Fruchard, Y.; Colome, J.; Malet, J.C.; Berlin, M.; Duverger de Cuy, G.; Justin, J.; Duco, J.

    1976-01-01

    In fast reactors, the risk of sodium fires must be analyzed in detail and the consequences of an accidental fire must be known precisely. Beyond the search for prevention and detection means, techniques must be developed to set up a limit to damages created by an accidental fire: extinguishing, aerosol confinement, protection of the reactor structures. The program developed by the Nuclear Safety Department of the Commissariat a l'Energie Atomique to solve these various problems is described. The main results and their applications to the Super-Phenix reactor are presented [fr

  11. Recent Analyses of Phenix End of Life Tests and Perspectives

    International Nuclear Information System (INIS)

    Fontaine, B.; Martin, L.; Prulhière, G.; Eschbach, R.; Portier, J.-L.; Masoni, P.; Tauveron, N.; Bavière, R.; Verwaerde, D.; Hamy, J.-M.

    2013-01-01

    Conclusion: • End of Life tests performed at PHENIX in 2009 gathered a lot of information concerning thermalhydraulics, core physics and fuel behavior in SFR cores. • The analysis of these tests is still undergoing for some of them, involving international collaborations. • To better understand the measurements, complex models are developed thanks to recent computer science progress: • thermalhydraulics: coupling CFD and system codes neutronics: - perturbation theory applied to Bateman equations - model of distorted core; • mechanics: fluid-structure interaction. The test results allow to validate these developments, which could be applied in the future for new SFR design

  12. Neutronic analysis concerning the utilization of mixed U N-Pu N nitride fuel for fast reactors

    International Nuclear Information System (INIS)

    Renke, C.A.C.; Batista, J.L.; Waintraub, M.; Santos Bastos, W. dos; Brito Aghina, L.O. de.

    1991-08-01

    Neutronic behavior of mixed UN-PuN nitride fuel in substitution of the mixed oxide U O 2 - Pu O 2 for fast reactors is discussed with focus on Super Phenix I. Characteristics parameters of both cores are calculated and compared and the results presented show a great advantage for the nitride fuel, pointing out a larger performance of fuel elements in the core and an effective reduction of reactivity loss during the cycle. (author)

  13. Fast reactors worldwide

    International Nuclear Information System (INIS)

    Hall, R.S.; Vignon, D.

    1985-01-01

    The paper concerns the evolution of fast reactors over the past 30 years, and their present status. Fast reactor development in different countries is described, and the present position, with emphasis on cost reduction and collaboration, is examined. The French development of the fast breeder type reactor is reviewed, and includes: the acquisition of technical skills, the search for competitive costs and the spx2 project, and more advanced designs. Future prospects are also discussed. (U.K.)

  14. The internal core catcher in Super Phenix 1

    International Nuclear Information System (INIS)

    Le Rigoleur, C.; Kayser, G.; Maurin, G.; Magnon, B.

    1982-07-01

    The internal core catcher in SUPER PHENIX 1 is described here in some detail. The fuel retention capabilities are presented for situations of increasing severity. The first situation corresponds to the core catcher design. It relates to a hypothetical subassembly accident that would cause a limited quantity of fuel, corresponding to the mass of seven subassemblies, to be deposited on the core catcher. For this situation and at all levels of the analysis, the most conservative assumptions are made in order to prove the integrity of the core catcher. The second situation corresponds to a hypothetical larger core melt accident. In this case, for some of the parameters, assumptions are made that correspond to the most likely situations based on engineering considerations. Then the maximum retention capabilities are presented

  15. CONCEPTUAL DESIGN REPORT FOR A FAST MUON TRIGGER

    Energy Technology Data Exchange (ETDEWEB)

    OBRIEN,E.; BASYE, A.; ISENHOWER, D.; JUMPER, D.; SPARKS, N.; TOWELL, R.; WATTS, C.; WOOD, J.; WRIGHT, R.; HAGGERTY, J.; LYNCH, D.; BARISH, K.; EYSER, K.O.; SETO, R.; HU, S.; LI, X.; ZHOU, S.; GLENN, A.; KINNEY, E.; KIRILUK, K.; NAGLE, J.; CHI, C.Y.; SIPPACH, W.; ZAJC. W.; BUTLER, C.; HE, X.; OAKLEY, C.; YING, J.; BLACKBURN, J.; CHIU, M.; PERDEKAMP, M.G.; KIM, Y.J.; KOSTER, J.; LAYTON, D.; MAKINS, N.; MEREDITH, B.; NORTHACKER, D.; PENG, J.-C.; SEIDL, R.; THORSLAND, E.; WADHAMS, S.; WILLIAMSON, S.; YANG, R.; HILL, J.; KEMPEL, T.; LAJOIE, J.; SLEEGE, G.; VALE, C.; WEI, F.; SAITO, N.; HONG, B.; KIM, B.; LEE, K.; LEE, K.S.; PARK, S.; SIM, K.-S.; AOKI, K.; DAIRAKU, S.; IMAI, K.; KARATSU, K.; MURAKAMI, T.; SATO, A.; SENZAKA, K.; SHOJI, K.; TANIDA, K.; BROOKS, M.; LEITCH, M.; ADAMS, J.; CARINGI, A.; FADEM, B.; IDE, J.; LICHTENWALNER, P.; FIELDS, D.; MAO, Y.; HAN, R.; BUNCE, G.; XIE, W.; FUKAO, Y.; TAKETANI, A.; KURITA, K.; MURATA, J.; (PHENIX COLLABORATION)

    2007-08-01

    This document is a Conceptual Design Report for a fast muon trigger for the PHENIX experiment that will enable the study of flavor separated quark and anti-quark spin polarizations in the proton. A powerful way of measuring these polarizations is via single spin asymmetries for W boson production in polarized proton-proton reactions. The measurement is done by tagging W{sup +} and W{sup -} via their decay into high transverse momentum leptons in the forward directions. The PHENIX experiment is capable of measuring high momentum muons at forward rapidity, but the current online trigger does not have sufficient rejection to sample the rare leptons fromW decay at the highest luminosities at the Relativistic Heavy Ion Collider (RHIC). This Report details the goals, design, R&D, and schedule for building new detectors and trigger electronics to use the full RHIC luminosity to make this critical measurement. The idea for W boson measurements in polarized proton-proton collisions at RHIC was first suggested by Jacques Soffer and Claude Bourrely in 1995. This prompted the RIKEN institute in Japan to supply funds to build a second muon arm for PHENIX (south muon arm). The existence of both a north and south muon arm makes it possible to utilize a Z{sup 0} sample to study and control systematic uncertainties which arise in the reconstruction of high momentum muons. This document has its origins in recommendations made by a NSAC Subcommittee that reviewed the U.S. Heavy Ion Physics Program in June 2004. Part of their Recommendation 1 was to 'Invest in near-term detector upgrades of the two large experiments, PHENIX and STAR'. In Recommendation 2 the subcommittee stated '- detector improvements proceed at a rate that allows a timely determination of the flavor dependence of the quark-antiquark sea polarization through W-asymmetry measurements' as we are proposing here. On September 13, 2004 DOE requested from BNL a report articulating a research plan for

  16. The role of materials in the analysis of fast breeder reactor components

    International Nuclear Information System (INIS)

    Aubert, Michel; Petrequin, Pierre.

    1982-09-01

    The analysis of fast breeder reactor components involves the knowledge of certain properties of the materials used. The latter consist of the following: - a body of data required for calculations, including allowable stresses and fatigue strength, as well as the rules applicable to these data, - a number of qualitative requirements serving to guarantee that the quality of the material fully justifies the use of the previously established elements. This duality of concerns is illustrated by some recent examples which occured during the construction of the Super Phenix reactor [fr

  17. Simulation of Phenix EOL Asymmetric Test

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Kwi Seok; Lee, Kwi Lim; Choi, Chi Woong; Kang, Seok Hun; Chang, Won Pyo; Jeong, Hae Yong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    The asymmetric test of End-Of-Life (EOL) tests on the Phenix plant was used for the evaluation of the MARS-LMR in the Generation IV frame as a part of the code validation. The purpose of the test is to evaluate the ability of the system code to describe asymmetric situations and to identify important phenomena during asymmetrical transient such as a three dimensional effect, buoyancy influence, and thermal stratification in the hot and cold pools. 3-dimensional sodium coolant mixing in the pools has different characteristics from the one dimensional full instantaneous mixing. The velocities and temperatures at the core outlet level differ at each sub-assembly and the temperature in the center of the hot pool may be high because the driver fuels are located at the center region. The temperatures in the hot pool are not the same in the radial and axial locations due to the buoyancy effect. The temperatures in the cold pool also differ along with the elevations and azimuthal directions due to the outlet location of IHX and the thermal stratification

  18. Geology and mineral resources of the Johnson City, Phenix City, and Rome 10 x 20 NTMS quadrangles

    International Nuclear Information System (INIS)

    Karfunkel, B.S.

    1981-11-01

    This document provides geologic and mineral resources data for the Savannah River Laboratory-National Uranium Resource Evaluation hydrogeochemical and stream-sediment reports for the Johnson City, Phenix City, and Rome 1 0 x 2 0 National Topographic Map Series quadrangles in the southeastern United States

  19. Signatures of color glass condensate: Forward azimuthal angle di-hadron correlations in PHENIX

    Energy Technology Data Exchange (ETDEWEB)

    Meredith, Beau, E-mail: bmeredi2@uiuc.ed [University of Illinois at Urbana Champaign, 1110 W Green St, Urbana, IL, 61801 (United States)

    2011-03-15

    Measurements using the PHENIX forward detectors in high energy deuteron-gold collisions make it possible to study cold nuclear matter effects in nucleon structure at low x. The high gluon densities in Lorentz-contracted gold nuclei make it possible to probe for gluon saturation or Color Glass Condensate effects. Past RHIC experiments have shown a suppression in nuclear modification factors (R{sub dA}, R{sub cp}) for {radical}(s{sub NN})=200 GeVd+Au collisions in the forward (deuteron) direction. Multiple theories can explain the observed suppression (including saturation), but a conclusive measurement discriminating between the models has yet to be carried out. Two new forward electromagnetic calorimeters (Muon Piston Calorimeters, -3.7<{eta}<-3.1, 3.1<{eta}<3.9) allow the PHENIX experiment to further study forward di-hadron correlations, which have been predicted to show dramatic effects due to gluon saturation. In particular, azimuthal correlations of di-hadron pairs at different pseudorapidities will be shown; the forward pseudorapidity correlations are especially interesting because it is expected that they provide a test of gluon saturation down to x{approx}10{sup -3} in the Au nucleus. The analysis presented is based on the high integrated luminosity data sample of d+Au collisions at {radical}(s{sub NN})=200 GeV taken at RHIC in 2008.

  20. Theory, design, and operation of liquid metal fast breeder reactors, including operational health physics

    International Nuclear Information System (INIS)

    Adams, S.R.

    1985-10-01

    A comprehensive evaluation was conducted of the radiation protection practices and programs at prototype LMFBRs with long operational experience. Installations evaluated were the Fast Flux Test Facility (FFTF), Richland, Washington; Experimental Breeder Reactor II (EBR-II), Idaho Falls, Idaho; Prototype Fast Reactor (PFR) Dounreay, Scotland; Phenix, Marcoule, France; and Kompakte Natriumgekuhlte Kernreak Toranlange (KNK II), Karlsruhe, Federal Republic of Germany. The evaluation included external and internal exposure control, respiratory protection procedures, radiation surveillance practices, radioactive waste management, and engineering controls for confining radiation contamination. The theory, design, and operating experience at LMFBRs is described. Aspects of LMFBR health physics different from the LWR experience in the United States are identified. Suggestions are made for modifications to the NRC Standard Review Plan based on the differences

  1. Theory, design, and operation of liquid metal fast breeder reactors, including operational health physics

    Energy Technology Data Exchange (ETDEWEB)

    Adams, S.R.

    1985-10-01

    A comprehensive evaluation was conducted of the radiation protection practices and programs at prototype LMFBRs with long operational experience. Installations evaluated were the Fast Flux Test Facility (FFTF), Richland, Washington; Experimental Breeder Reactor II (EBR-II), Idaho Falls, Idaho; Prototype Fast Reactor (PFR) Dounreay, Scotland; Phenix, Marcoule, France; and Kompakte Natriumgekuhlte Kernreak Toranlange (KNK II), Karlsruhe, Federal Republic of Germany. The evaluation included external and internal exposure control, respiratory protection procedures, radiation surveillance practices, radioactive waste management, and engineering controls for confining radiation contamination. The theory, design, and operating experience at LMFBRs is described. Aspects of LMFBR health physics different from the LWR experience in the United States are identified. Suggestions are made for modifications to the NRC Standard Review Plan based on the differences.

  2. The French emirs of uranium

    International Nuclear Information System (INIS)

    Lucas, N.

    1978-01-01

    The French energy plan is described under the following heads: structure of supply/use; nuclear energy; oil consumption; coal consumption; gas consumption; energy conservation; renewable resources. The section on nuclear energy covers: nuclear programmes, uranium supplies (mining and enrichment), fuel fabrication and reprocessing, finance and economics, political and administrative aspects, nuclear trade, development of fast breeder reactor. (U.K.)

  3. Studying Cold Nuclear Matter with the MPC-EX of PHENIX

    Science.gov (United States)

    Grau, Nathan; Phenix Collaboration

    2017-09-01

    Highly asymmetric collision systems, such as d+Au, provide a unique environment to study cold nuclear matter. Potential measurements range from pinning down the modification of the nuclear wave function, i.e. saturation, to studying final state interactions, i.e. energy loss. The PHENIX experiment has enhanced the muon piston calorimeter (MPC) with a silicon-tungsten preshower, the MPC-EX. With its fine segmentation the MPC-EX extends the photon detection capability at 3 < | η | < 3.8. In this talk we review the current status of the detector, its calibration, and its identification capabilities using the 2016 d+Au dataset. We also discuss the specific physics observables the MPC-EX can measure.

  4. 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)

  5. Development of a FBR fuel bundle-duct interaction analysis code-BAMBOO. Analysis model and verification by Phenix high burn-up fuel subassemblies

    International Nuclear Information System (INIS)

    Uwaba, Tomoyuki; Ito, Masahiro; Ukai, Shigeharu

    2005-01-01

    The bundle-duct interaction analysis code ''BAMBOO'' has been developed for the purpose of predicting deformation of a wire-wrapped fuel pin bundle of a fast breeder reactor (FBR). The BAMBOO code calculates helical bowing and oval-distortion of all the fuel pins in a fuel subassembly. We developed deformation models in order to precisely analyze the irradiation induced deformation by the code: a model to analyze fuel pin self-bowing induced by circumferential gradient of void swelling as well as thermal expansion, and a model to analyze dispersion of the orderly arrangement of a fuel pin bundle. We made deformation analyses of high burn-up fuel subassemblies in Phenix reactor and compared the calculated results with the post irradiation examination data of these subassemblies for the verification of these models. From the comparison we confirmed that the calculated values of the oval-distortion and bowing reasonably agreed with the PIE results if these models were used in the analysis of the code. (author)

  6. Simulation of the core flowering End-of-life test realized on Phenix reactor

    International Nuclear Information System (INIS)

    Prulhiere, G.; Fontaine, B.; Frosio, T.

    2013-01-01

    After the definitive shutdown of the Phenix sodium cooled fast reactor and before its decommissioning, a final set of tests were performed covering core physics, fuel behavior and thermal hydraulics areas. In addition, the program included two tests related to the comprehension of the four negative reactivity transients experienced during the reactor operation in 1989 and 1990. One of these tests, called 'core flowering test' focused on the relation between sub-assemblies mechanical displacements and reactivity variations. This test was carried out by introducing a mechanical device pushing on the six fuel assemblies neighbors. This device was located at two different core positions: at the center and at a peripheral one. The reactivity effect induced by core flowering was measured at different temperatures in the range of 180 to 350 Celsius degrees. The simulation of such a test requires the use of a neutronic computing code which is not compelled to the definition of regular geometrical lattices. Moreover, a system permitting an easy and change-allowing way to define geometries and deformations is needed. That is why the use of a Monte Carlo code like TRIPOLI coupled to ROOT system was chosen to simulate this test. The displacement of each sub-assembly was estimated upstream of this study using the static mechanics code HARMONIE. To perform this calculations with a satisfying precision, several hundreds millions of neutrons particles were needed for the modelling. (author)

  7. Irradiation of mixed UO2-PuO2 oxide samples for fast neutron reactor fuel elements

    International Nuclear Information System (INIS)

    Mikailoff, H.; Mustelier, J.; Bloch, J.; Conte, M.; Hayet, L.; Lauthier, J.C.; Leclere, J.

    1968-01-01

    Thermal flux irradiation testings of small mixed oxide pellets UPuO 2 fuel elements were performed in support of the fuel reference design for the Phenix fast reactor. The effects of different parameters (stoichiometry, pellet density, pellet clad gap). on the behaviour of the oxide (temperature distribution, microstructural changes, fission gas release) were investigated in various irradiation conditions. In particular, the effect of fuel density decrease and power rate increase on thermal performances were determined on short term irradiations of porous fuels. (authors) [fr

  8. Application of a statistical methodology for the comprehension of corrosion phenomena on Phenix spent fuel pins

    International Nuclear Information System (INIS)

    Pantera, L.

    1992-11-01

    The maximum burnup of Phenix fuel elements is strongly conditioned by the internal corrosion of the steel cladding. This thesis is a part of a new study program on the corrosion phenomena. Based on the results of an experimental program during the years 1980-1990 its objective is the use of a statistical methodology for a better comprehension of the corrosion phenomena

  9. Data collection modules for the PHENIX experiment

    International Nuclear Information System (INIS)

    Chi, C.Y.; Cole, B.; Nagle, J.L.; Sippach, W.; Zajc, W.A.

    1998-01-01

    The data acquisition (DAQ) system for the PHENIX experiment is designed as a pipeline system with simultaneous triggering and readout. The maximum average level-1 (LVL1) trigger rate is 25 KHz. The DAQ system consists of Front-End Modules (FEM's), a level-1 (LVL1) trigger, data collection modules (DCM's) timing systems, slow controllers and an event builder (EVB). The data collection modules have the responsibility of collecting uncompressed LVL1 trigger event fragments from the FEM's. The DCM's provide buffering for up to five LVL1 events. The DCM's also perform zero suppression, error checking, data reformatting and outputting data to the event builder. In addition to the FEM data, the DCM's also receive primitives from LVL1 trigger system. These primitives are used for alignment checking on the FEM data packet. Additional trigger primitives can also be generated together with the FEM data. The DCM is hosted in a VME crate. VME is used as a means for maintenance and slow control. Data collection within the crate is done through a private data-way

  10. A review of the Italian fast reactor programme

    Energy Technology Data Exchange (ETDEWEB)

    Bruzzi, L; Pierantoni, F [CNEN Fast Reactor Programme, Bologna (Italy)

    1981-05-01

    In the frame of Italian nuclear program, this report deals with the current activities related to PEC reactor delay in construction and start-up, activities within the joint venture between Novatome, France and NIRA, Italy related to components for Super Phenix reactor, participation of NIRA in the Super Phenix studies covering technology of reactor components, reactor core, fuel, safety, fuel cycle technical and economical aspects, codes and standards.

  11. Calculation of the transmutation rates of Tc-99, I-129 and Cs-135 in the High Flux Reactor, in the Phenix Reactor and in a light water reactor

    International Nuclear Information System (INIS)

    Bultman, J.

    1992-04-01

    Transmutation of long-lived fission products is of interest for the reduction of the possible dose to the population resulting from long-term leakage of nuclear waste from waste disposals. Three isotopes are of special interest: Tc-99, I-129 and Cs-135. Therefore, experiments on transmutation of these isotopes in nuclear reactors are planned. In the present study, the possible transmutation rates and mass reductions are determined for experiments in High Flux Reactor (HFR) located in Petten (Netherlands) and in Phenix (France). Also, rates were determined for a standard Light Water Reactor (LWR). The transmutation rates of the 3 fission products will be much higher in HFR than in Phenix reactor, as both total flux and effective cross sections are higher. For thick targets the effective half lives are approximately 3, 2 and 7 years for Tc-99, I-129 and Cs-135 irradiation respectively in HFR and 22, 16 and 40 years for Tc-99, I-129 and Cs-135 irradiation in Phenix reactor. The transmutation rates in LWR are low. Only the relatively large power of LWR guarantees a large total mass reduction. Especially transmutation of Cs-135 will be very difficult in Phenix and LWR, clearly shown by the very long effective half lives of 40 and 100 years, respectively. (author). 7 refs.; 5 figs.; 7 tabs

  12. Fast reactor development program in France in 1999

    International Nuclear Information System (INIS)

    Leclere, Jacques; Teilland, C.; Astegiano, J.C.; Desreumaux, J.; Grenet, P.; Del Beccaro, R.; Vasile, A.

    2000-01-01

    The year 1999 was marked by important industrial reorganisations, especially concerning Framatome: the shareholding was modified, and at the end of the year the fusion of nuclear activities with those of Siemens was decided. The construction of the last N4 plants is completed, with no realisation expected in the near future; the decision on an EPR unit is not expected in the short term. The operation of the plants was satisfying, the availability is nevertheless lower than in 1998. Renovation, inspection and maintenance works were actively conducted at Phenix; decommissioning work was undertaken at Superphenix; the core unloading began in December. The R and D strategy was redefined; on fast reactors, work decreases on sodium and increases on other variants. International collaborations remain active. (author)

  13. Overview of french P and T programme and results for waste management

    International Nuclear Information System (INIS)

    Warin, D.; Courtois, C.

    2005-01-01

    We will present here the French program and an update on the progress made by the research conducted on partitioning and transmutation. Studies on partitioning and transmutation aim at isolating the most radio toxic long-lived elements present in the waste then at transmuting them through recycling in nuclear reactors, in order to change them into non-radioactive or shorter-lived elements. The partitioning of minor actinides (americium, curium and neptunium), followed by their transmutation, would reduce to a few hundred years the time necessary for the radiotoxicity of the vitrified waste to become similar to that contained in the natural uranium ore originally used. The feasibility of partitioning, which did not appear easily accessible at the time the research began since lanthanides and actinides have rather similar chemical properties, was nevertheless demonstrated in 2001 thanks to a series of tests conducted on solutions of dissolved spent fuel, in the CEA Atalante facility at Marcoule. The 2002-2005 program encompasses technological demonstration of the selected liquid-liquid process, with representative equipment, and economic evaluation of industrial implementation of partitioning. Studies on transmutation, which were initiated before the 1991 Law, rapidly led to concluding that transmutation of minor actinides (Americium, Curium, and Neptunium) was feasible in particular in fast neutron spectra. Results obtained confirm that the feasibility of transmutation is demonstrated, both in pressurized-water reactors (recycling and transmutation of plutonium, optionally but with more difficulty of americium and neptunium) and in advanced systems of nuclear-energy production (GEN IV fast-spectrum reactors, with recycling and transmutation of all heavy nuclides, uranium, plutonium, the minor actinides) or in dedicated incinerator reactors, either critical or sub critical. Work on transmutation is now focusing on technical elements necessary for the demonstration of

  14. Update on the FUTURIX-FTA Experiment in PHENIX

    International Nuclear Information System (INIS)

    Jaecki, P.; Pillon, S.; Warin, D.; Donnet, L.; Jorion, F.; Drin, N.; Hayes, S.L.; Kennedy, J.R.; Pasamehmetoglu, K.; Voit, S.L.; Haas, D.; Fernandez, A.

    2006-01-01

    Europe and the USA are following similar R and D partitioning and transmutation strategies to manage long lived waste, especially minor actinides. Actinide transmutation and recycle is presently being considered in dedicated systems such as Accelerator-Driven Systems (ADS), in Generation IV fast reactors, and in current light water reactors. In ADS, this leads to specific fuel formulations, highly enriched in Minor Actinides. Fertile uranium is excluded from ADS fuels to avoid the production of plutonium ('non-fertile or U-free fuels'). For low-fertile fuels, Uranium content is adjusted to achieve a conversion ratio of 0.25 or less and plutonium production is therefore limited. Very little information is available about the irradiation behaviour of the resulting fuel compositions. The FUTURIX-FTA experiment objective is to compare in similar and representative conditions the behaviour of fuels proposed for TRU burning. The FUTURIX-FTA program began in January 2003 and the irradiation in Phenix will start at the beginning of 2007. This progress report focuses on the latest results, R and D and irradiation test design which are almost complete. The paper has the following contents: I. Introduction; II. Fuel compositions; III. CERCER Fuels; 1. Design and safety considerations; 2. R and D on CERCER fuel fabrication; Preparation of (Pu,Am)O 2 by co-conversion; Fabrication of composites; Oxygen (O/M) stoichiometry, density and crystal structures of the actinide compounds; (Pu 0.2 Am 0.8 )O 2-x MgO Cercer Matrix; Microstructure and Porosity of the Compounds; IV. CERMET Fuels; 1. Design and safety considerations; 2. R and D on CERMET fuel fabrication; V. Metallic fuels; 1. Design and safety considerations; 2. R and D on CERMET fuel fabrication; VI. Nitride fuels; 1. Design and safety considerations;. R and D on NITRIDE fuel fabrication; II. Irradiation conditions; III. Conclusion. To summarize, preliminary design work is complete, and the final design will be fixed in 2006

  15. Analysis, design, and implementation of PHENIX on-line computing systems software using Shlaer-Mellor object-oriented analysis and recursive design

    International Nuclear Information System (INIS)

    Kozlowski, T.; Desmond, E.; Haggerty, J.

    1997-01-01

    An early prototype of the core software for on-line computing systems for the PHENIX detector at RHIC has been developed using the Shlaer-Mellor OOA/RD method, including the automatic generation of C++ source code using a commercial translation engine and open-quotes architectureclose quotes

  16. Measurement of J/{psi} production in proton-proton collisions by the PHENIX experiment

    Energy Technology Data Exchange (ETDEWEB)

    Bruner, Nichelle [University of New Mexico, Albuquerque, NM (United States)

    2004-07-01

    The PHENIX experiment at the Relativistic Heavy Ion Collider has measured J/{psi} production in proton-proton collisions at {radical}(s)= 200 GeV using data from the 2001-2002 collider run. Distributions of rapidity and transverse momentum are presented and compared with theoretical predictions. The total cross section and mean p{sub T} are calculated and compared to fixed-target results. The total J/{psi} cross section is 4.0{+-}0.6(stat){+-}0.6(sys){+-}0.4(abs){mu}b. The mean p{sub T} is 1.80{+-}0.23(stat){+-}0.16(sys) GeV/c. (orig.)

  17. Measurement of J/ψ production in proton-proton collisions by the PHENIX experiment

    International Nuclear Information System (INIS)

    Bruner, Nichelle

    2004-01-01

    The PHENIX experiment at the Relativistic Heavy Ion Collider has measured J/ψ production in proton-proton collisions at √(s)= 200 GeV using data from the 2001-2002 collider run. Distributions of rapidity and transverse momentum are presented and compared with theoretical predictions. The total cross section and mean p T are calculated and compared to fixed-target results. The total J/ψ cross section is 4.0±0.6(stat)±0.6(sys)±0.4(abs)μb. The mean p T is 1.80±0.23(stat)±0.16(sys) GeV/c. (orig.)

  18. Neutron characteristics of the Super-Phenix 1 reactor at Creys-Malville

    International Nuclear Information System (INIS)

    Giacometti, C.; Bouget, Y.H.; Hammer, P.; Lyon, F.; Salvatores, M.; Sicard, B.; Pipaud, J.Y.

    1980-01-01

    The paper describes the method used to determine the critical enrichments for the first loading of the Super-Phenix reactor and the correction factors (together with their uncertainties) applied to the data calculated from the CARNAVAL IV code. These enrichments must be chosen so as to conform to the planned operating conditions of the reactor: nominal power of the pressure vessels, lifetime of the in-pile assemblies. Allowance for uncertainties of neutronic origin and those associated with the fabrication of the fuel pins calls for an over-enrichment of the first loading by approximately 4 per cent. An analysis is made of the effects of this over-enrichment on the core characteristics, which have to remain compatible with the established limits. (author)

  19. Timing and control requirements for a 32-channel AMU-ADC ASIC for the PHENIX detector

    International Nuclear Information System (INIS)

    Emery, M.S.; Ericson, M.N.; Britton, C.L. Jr.

    1998-01-01

    A custom CMOS Application Specific Integrated Circuit (ASIC) has been developed consisting of an analog memory unit (AMU) has been developed consisting of an analog memory unit (AMU) and analog to digital converter (ADC), both of which have been designed for applications in the PHENIX experiment. This IC consists of 32 pipes of analog memory with 64 cells per pipe. Each pipe also has its own ADC channel. Timing and control signal requirements for optimum performance are discussed in this paper

  20. Behaviour and microstructure of stainless steels irradiated in the french fast breeder reactors

    International Nuclear Information System (INIS)

    Dubuisson, P.; Gilbon, D.

    1991-01-01

    The burn-up of Fast Breeder Reactors is limited by the irradiation induced dimensional changes and mechanical properties of structural materials used for replaceable in-core components. This paper describes the behaviour improvements and also the radiation-induced microstructures of the different steels used for fuel pin cladding and wrapper tubes in French reactors. Materials of fuel pin cladding are austenitic steels whose main problem is swelling. Improvements in swelling resistance by cold-working, titanium additions and modifications of matrix (Fe-Cr-Ni) from SA 316 to CW 15-15 Ti are shown. These improvements are correlated with a best stability of microstructure under irradiation. Beneficial effects of phosphorus addition and multistabilisation (NbVTi) on radiation induced microstructure and swelling resistance are also shown. Austenitic steels used for wrapper tubes are limited both by swelling and by void embrittlement. The ferritic F17 (17Cr), ferritic-martensitic EM12 (9Cr-2MoNbV) and martensitic EM10 (9Cr-1Mo) steels present high swelling resistance. Nevertheless radiation-induced embrittlement is observed in EM12 and especially in F17. This embrittlement results from a fine and uniform radiation enhanced precipitation in ferrite grains. By contrast, the microstructure of fully martensitic EM10 steel is mush more stable and its ductile-brizzle transition temperature stays below 0 0 C. 12 figs

  1. Water leak detection in steam generator of SUPER PHENIX

    International Nuclear Information System (INIS)

    Brunet, M.; Garnaud, P.; Ghaleb, D.; Kong, N.

    1988-01-01

    With the intent of detecting water leaks inside steam generators, we developed a third system, called acoustic detector, to complement hydrogen detectors and rupture disks (burst disks). The role of the acoustic system is to enable rapid intervention in the event of a leak growing rapidly which could rupture neighbouring tubes. In such a case, the detectable flow rate of the leak varies from a few tens of g/s to a few hundred g/s. At the SUPER PHENIX, three teams work in [20-100 kHz] and CEA/STA* [50-300 kHz]. The simulation of water leaks in the steam generator by the argon injections performed to date at 50% of the rated power has shown promising results. An anomaly in the evolution of the background noise at more than 50% loading of one of the two instrumented steam generators would make difficult any extrapolation to full power behaviour. (author)

  2. The integration of fast reactor to the fuel cycle in Slovakia

    International Nuclear Information System (INIS)

    Zajac, R.; Darilek, P.; Necas, V.

    2009-01-01

    A very topical problem of nuclear power is the fuel cycle back-end. One of the options is a LWR spent fuel reprocessing and a fissile nuclides re-use in the fast reactor. A large amount of spent fuel has been stored in the power plant intermediate storage during the operation of WWER-440 reactors in Slovakia. This paper is based on an analysis of Pu and minor actinides content in actual WWER-440 spent fuel stored in Slovakia. The next part presents the possibilities of reprocessing and Pu re-use in fast reactor under Slovak conditions. The fuel cycle consisting of the WWER-440 reactor, PUREX reprocessing plant and a sodium fast reactor was designed. The last section compares two parts of this fuel cycle: one is UOX cycle in WWER-440 reactor and the other is cycle in the fast reactor - SUPER PHENIX loaded with MOX fuel (Pu + Minor Actinides). The starting point is a single recycling of Pu from WWER-440 in the fission products. The next step is multi recycling of Pu in the fission products to obtain equilibrium cycle. This article is dealing with the solution of power production and fuel cycle indicators. All kinds of calculations were performed by computer code HELIOS 1.10. (Authors)

  3. The integration of fast reactor to the fuel cycle in Slovakia

    International Nuclear Information System (INIS)

    Zajac, R.; Darilek, P.; Necas, V.

    2009-01-01

    A very topical problem of nuclear power is the fuel cycle back-end. One of the options is a LWR spent fuel reprocessing and a fissile nuclides re-use in the fast reactor. A large amount of spent fuel has been stored in the power plant intermediate storage during the operation of VVER-440 reactors in Slovakia. This paper is based on an analysis of Pu and minor actinides content in actual VVER-440 spent fuel stored in Slovakia. The next part presents the possibilities of reprocessing and Pu re-use in fast reactor under Slovak conditions. The fuel cycle consisting of the VVER-440 reactor, PUREX reprocessing plant and a sodium fast reactor was designed. The last section compares two parts of this fuel cycle: one is UOX cycle in VVER-440 reactor and the other is cycle in the fast reactor - SUPER PHENIX loaded with MOX fuel (Pu + Minor Actinides). The starting point is a single recycling of Pu from VVER-440 in the FR. The next step is multirecycling of Pu in the FR to obtain equilibrium cycle. This article is dealing with the solution of power production and fuel cycle indicators. All kinds of calculations were performed by computer code HELIOS 1.10. (authors)

  4. The Economics and Politics of Louisiana’s Latest French Renaissance

    OpenAIRE

    Degrave, Jérôme

    2014-01-01

    Louisiana French is dying. With fewer than 160,000 speakers and an extremely limited trans-generational transmission, the language of the Cajuns is fast disappearing although the main facets of their culture – food and music – continue to enjoy international fame. This paradox is not the only one: Louisiana is the only state in the USA which took the trouble to endow itself with a public agency meant to defend and diffuse a minority language, namely French. Created in 1968 by an act of the Lo...

  5. Energetic transitions by the French engineers and scientists

    International Nuclear Information System (INIS)

    Wiltz, Bruno

    2014-01-01

    The energetic transition concerns the French scientists and engineers very much (1 million) because they are a lot involved in research, innovation, development, exploitation and generally in industry, in a field of fast-changing environment and of vital national interest, which, despite the absence of dominant classical resources, has remarkable potentials. (O.M.)

  6. 1001 easy French phrases

    CERN Document Server

    McCoy, Heather

    2010-01-01

    The perfect companion for tourists and business travelers in France and other places where the French language is spoken, this book offers fast, effective communication. More than 1,000 basic words, phrases, and sentences cover everything from asking directions and renting a car to ordering dinner and finding a bank.Designed as a quick reference tool and an easy study guide, this inexpensive and easy-to-use book offers completely up-to-date terms for modern telecommunications, idioms, and slang. The contents are arranged for quick access to phrases related to greetings, transportation, shoppin

  7. Fine pitch and low material readout bus in the Silicon Pixel Vertex Tracker for the PHENIX Vertex Tracker upgrade

    International Nuclear Information System (INIS)

    Fujiwara, Kohei

    2010-01-01

    The construction of the Silicon Pixel Detector is starting in spring 2009 as project of the RHIC-PHENIX Silicon Vertex Tracker (VTX) upgrade at the Brookhaven National Laboratory. For the construction, we have developed a fine pitch and low material readout bus as the backbone parts of the VTX. In this article, we report the development and production of the readout bus.

  8. Hydrogen and acoustic detection in steam generators of Super Phenix power plant

    International Nuclear Information System (INIS)

    Kong, N.; Le Bris, A.; Berthier, P.

    1986-05-01

    During the isothermal tests of Super-Phenix, two types of measurements were made on the steam generators with regard to the detection of water leaks into the sodium: - the first measurements enabled us to determine the characteristics (sensitivity, response time) of the hydrogen detectors that are already operational for the filling with water and the power operation of the steam generators. They also provided the basis for developing a prototype system for detecting very small water leaks (microleak phase). The other measurements concern the qualification tests of acoustic detectors which have been fitted for the first time to a major industrial installation. The results obtained are very satisfactory but final validation of the acoustic method will only occur after the full-power tests [fr

  9. Measurements of negative reactivity in Masurca and Phenix control rods: Prospects for Superphenix

    International Nuclear Information System (INIS)

    Gauthier, J.C.; Petiot, R.; Coulon, P.; Giese, H.; West, J.P.

    1986-01-01

    Experimental assessment of the negative reactivity of the control rods in an industrial reactor has recently been the subject of numerous studies conducted in the light of forthcoming startup tests on the core of Superphenix. Representative tests have been carried out both on Phenix and on the Masurca critical mockup, and a test programme for Superphenix has been drawn up. Subcritical measurements (source multiplication technique) have been carried out on Phenix without absolute measurement of a standard. However, a precise relative interpretation using two counters demonstrates good agreement following the correction of spatial effects. The chief value of the rod drop measurements conducted on Masurca was that it provided a means of cross-checking the kinetic method to be validated against a standard source multiplication method. The results demonstrate complete agreement between the two methods. The acceptability of the rod drop method is therefore considered to be established. The programme foreseen for startup of Superphenix and the objectives which have been set are briefly indicated. The calculation methods to be used in respect of the startup tests have been established on the basis of experience gained through interpreting the experiments conducted in the course of the Racine (Masurca) programme. An analysis of these experiments included, among other things, a parametric study that has made it possible to devise a standard calculation method for predicting Superphenix rod worth values. The main feature is a scattering calculation with three energy groups and three dimensions. Two-dimensional scattering and transport calculations are therefore necessary in order to define the corrective factors to be applied to this initial result. The final result of this analysis is thus made equivalent to a 25-energy-group transport calculation with an extremely small spatial mesh

  10. Comparison of the methods of seismic analysis applicable to fast reactors in the EEC countries

    International Nuclear Information System (INIS)

    Defalque, M.; Kunsch, P.; Preumont, A.

    1986-01-01

    The countries in the Community which are concerned by this study are those currently involved in the operation or development of fast reactors, namely: FRANCE (Phenix - Superphenix), FRG - BELGIUM - THE NETHERLANDS associated within DeBeNe (SNR - 300), UNITED KINGDOM (UK) (PFR-CDFR), ITALY (PEC). The first aim of the study is to enumerate the common points and differences in the national rules and regulations for the seismic analysis of fast breeder reactors. Such divergences may be encountered at different design stages, namely: in the definition of the seismic input data, in the choice of design limits and in the degree of conservatism applied to the calculation methods employed. For every one of these three stages, it is necessary to identify the points likely to influence the results of the analysis and consequently the over-all safety margin with regard to the event concerned. 73 refs

  11. Prompt photon measurements with the PHENIX MPC-EX detector

    Science.gov (United States)

    Campbell, Sarah

    2013-04-01

    The MPC-EX detector is a preshower extension to PHENIX's Muon Piston Calorimeter (MPC). It consists of eight layers of alternating W absorber and Si mini-pad sensors. Located at forward rapidity, 3.180 GeV, allowing the measurement of prompt photons using the double ratio method. At forward rapidities, prompt photons are dominated by direct photons produced by quark-gluon Compton scattering. In transversely polarized p+p collisions, the prompt photon single spin asymmetry measurement, AN, will resolve the sign discrepancy between the Sivers and twist-3 extractions of AN. In p+Au collisions, the prompt photon RpAu will quantify the level of gluon saturation in the Au nucleus at low-x, 10-3, with a projected systematic error band a factor of four smaller than EPS09's current allowable range. The MPC-EX detector will expand our understanding of gluon nuclear parton distribution functions, providing information about the initial state of heavy ion collisions, and clarify how valence parton's pT and spin correlate to the proton spin.

  12. Water leak detection in steam generator of Super Phenix

    International Nuclear Information System (INIS)

    Kong, N.; Brunet, M.; Garnaud, P.; Ghaleb, D.

    1990-01-01

    With the intent of detecting water leaks inside steam generators, we developed a third system, called acoustic detector, to complement hydrogen detectors and rupture disks (burst disks). The role of the acoustic system is to enable rapid intervention in the event of a leak growing rapidly which could rupture neighbouring tubes. In such a case, the detectable flow rate of the leak varies from a few tens of g/s to a few hundred g/s. At the Super Phenix, three teams work in parallel in complementary frequency bands: EDF (0-20 kHz), CEA/SPCI (20-100 kHz) and CEA/STA (50-300 kHz). The simulation of water leaks in the steam generator by the argon injections performed to date at 50% of the rated power has shown promising results. An anomaly in the evolution of the background noise at more than 50% loading of one of the two instrumented steam generators would make difficult any extrapolation to full power behaviour. 5 refs, 6 figs, 1 tab

  13. French ESPN order, codes and nuclear industry requirements

    International Nuclear Information System (INIS)

    Laugier, C.; Grandemange, J.M.; Cleurennec, M.

    2010-01-01

    Work on coding safety regulations applicable to large equipment was undertaken in France as of 1978 to accompany the construction of a French nuclear plant. The needs of manufacturers were threefold: translate the design rules from the American licensor, meet the safety objectives expressed in French regulations published at that time through coding of industrial practices (order of February 26, 1974) and stabilize the work reference system between the operator - consultant - and the manufacturer responsible for applying technical recommendations. Significant work was carried out by AFCEN (the French Association for the Design, Construction and Operating Supervision of the equipment for Electronuclear boilers), an association created for this purpose, leading to the publication of a collection of rules related to mechanical equipment for pressurised water reactors, RCC-M and RSE-M, which will be discussed later, and also in several other technical fields: particularly mechanical equipment in fast neutron reactors, RCC-MR, electricity (RCC-E), and fuel (RCC-C). (authors)

  14. Remote maintenance in TOR fast reactor fuel reprocessing facility

    International Nuclear Information System (INIS)

    Eymery, R.; Constant, M.; Malterre, G.

    1986-11-01

    The TOR facility which is undergoing commissioning tests has a capacity of 5 T. HM/year which is enough for reprocessing all the Phenix fuel, with an excess capacity which is to be used for other fast reactors fuels. It is the result of enlargement and renovation of the old Marcoule pilot facility. A good load factor is expected through the use of equipment with increased reliability and easy maintenance. TOR will also be used to test new equipment developed for the large breeder fuel reprocessing plant presently in the design stage. The latter objective is specifically important for the parts of the plant involving mechanical equipment which are located in a new building: TOR 1. High reliability and flexibility will be obtained in this building thanks to the attention given to the integrated remote handling system [fr

  15. [Fast food promotes weight gain].

    Science.gov (United States)

    Stender, Steen; Dyerberg, Jørn; Astrup, Arne V

    2007-05-07

    The total amounts of fat in a fast food menu consisting of French fries and fried Chicken Nuggets from McDonald's and KFC, respectively, bought in 35 different countries vary from 41 to 71 gram. In most countries the menu contained unacceptably high amounts of industrially-produced trans fat which contributes to an increased risk of ischaemic heart disease, weight gain, abdominal fat accumulation and type 2 diabetes. The quality of the ingredients in fast food ought to be better and the size of the portions smaller and less energy-dense so that frequent fast food meals do not increase the risk of obesity and diseases among customers.

  16. First application of the Bailey Control Micro-Z system. Control of sodium purity in the Super Phenix reactor

    International Nuclear Information System (INIS)

    Hureau, J.-C.

    1979-01-01

    The system for testing the purity of sodium in the Super Phenix reactor at Crey-Malville is one of the very first applications of the 'μz' Bailey Control system which, as is generally known, uses a microprocessor on each regulator. This characteristic is cleverly exploited here for discontinuous regulation, in stages, of an analog parameter: temperature, with a quite remarkable flexibility of use and an extremely reduced volume of equipment [fr

  17. Fast breeder fuel cycle, worldwide and French prospects

    International Nuclear Information System (INIS)

    Rapin, M.

    1982-01-01

    A review is given of fast breeder fuel cycle development from both the technological and the economical points of view. LMFBR fuel fabrication, reactor operation, spent fuel storage and transportation, reprocessing and fuel cycle economics are topics considered. (U.K.)

  18. Overview of the French program in chemical separations and transmutation

    International Nuclear Information System (INIS)

    Baudin, G.

    1993-01-01

    A long-range effort has begun in France that is aimed at the reduction of the volume and activity level of wastes containing long half-life radionuclides. This effort constitutes the SPIN (SeParations-INcineration) Program which investigates separations techniques that can improve current reprocessing technologies coupled with destruction of long-lived species through transmutation. Removal and destruction of specific radionuclides (e.g., neptunium, americium, technetium, iodine, cesium, and strontium) will be emphasized. Advanced solvent extraction chemistry focusing, for example, on development and implementation of diamides for actinide-lanthanide separations constitutes an important component of the SPIN program. The second component of the program focuses on inventory reductions through transmutation of such long-lived nuclides in fast reactor systems (Super Phenix). Accelerator-based systems are also being evaluated as a possible long-term option. Both of these components of the SPIN program are aimed at further reduction of the potential radiotoxicity and radiological impact of high-level wastes destined for geological storage. In this presentation, major activities of the SPIN Program will be described with emphasis on activities related to advanced chemical separations

  19. Fast Reactor Physics. Vol. II. Proceedings of a Symposium on Fast Reactor Physics and Related Safety Problems

    International Nuclear Information System (INIS)

    1968-01-01

    Proceedings of a Symposium organized by the IAEA and held in Karlsruhe, 30 October - 3 November 1967. The meeting was attended by 183 scientists from 23 countries and three international organizations. Contents: (Vol.1) Review of national programmes (5 papers); Nuclear data for fast reactors (12 papers); Experimental methods (3 papers); Zoned systems (7 papers); Kinetics (7 papers). (Vol.11) Fast critical experiments (8 papers); Heterogeneity in fast critical experiments (5 papers); Fast power reactors (13 papers); Fast pulsed reactors (3 papers); Panel discussion. Each paper is in its original language (50 English, 11 French and 3 Russian) and is preceded by an abstract in English with a second one in the original language if this is not English. Discussions are in English. (author)

  20. The new French Development aid towards French-speaking Africa

    OpenAIRE

    Konate, Sindou Michel

    2013-01-01

    This project is focused on French president François Hollande new policy initiation around French Development assistance issue, particularly to French speakingAfrica South of the Sahara. President Hollande wishes to distance himself from the practices of his predecessors on French Public Development Assistance toward its former African colonies This project is focused on French president François Hollande new policy initiation around French Development assistance issue, particularly to Fre...

  1. Probing medium-induced energy loss with direct jet reconstruction in p+p and Cu+Cu collisions at PHENIX

    International Nuclear Information System (INIS)

    Lai, Y.-S.

    2009-01-01

    We present the application of a new jet reconstruction algorithm that uses a Gaussian filter to locate and reconstruct the jet energy to p+p and heavy ion data from the PHENIX detector. This algorithm is combined with a fake jet rejection scheme that provides efficient jet reconstruction with an acceptable fake rate. We show our first results on the measured jet spectra, and on jet-jet angular correlation in p+p and Cu+Cu collisions.

  2. General presentation of the core mechanical behaviour approach in France

    International Nuclear Information System (INIS)

    Bernard, A.; Dorsselaere, J.P. van

    1984-01-01

    This French review paper presents the evolution along time of the FBR core mechanical behaviour approach, from RAPSODIE to SPX2, through PHENIX and SPX1: core designs, knowledge of the irradiation laws, project criterias, calculation codes, and R and D fields. (author)

  3. What French for Gabonese French lexicography? | Assam | Lexikos

    African Journals Online (AJOL)

    This paper is a response to Mavoungou (2013a) who has pleaded for the production of a dictionary of Gabonese French as variant B of the French language. The paper intends to com-prehend the concept of "Gabonese French". It gives an outline of the situation of French within the language diversity of Gabon as a ...

  4. Analysis of Phenix end-of-life natural convection test with the MARS-LMR code

    International Nuclear Information System (INIS)

    Jeong, H. Y.; Ha, K. S.; Lee, K. L.; Chang, W. P.; Kim, Y. I.

    2012-01-01

    The end-of-life test of Phenix reactor performed by the CEA provided an opportunity to have reliable and valuable test data for the validation and verification of a SFR system analysis code. KAERI joined this international program for the analysis of Phenix end-of-life natural circulation test coordinated by the IAEA from 2008. The main objectives of this study were to evaluate the capability of existing SFR system analysis code MARS-LMR and to identify any limitation of the code. The analysis was performed in three stages: pre-test analysis, blind posttest analysis, and final post-test analysis. In the pre-test analysis, the design conditions provided by the CEA were used to obtain a prediction of the test. The blind post-test analysis was based on the test conditions measured during the tests but the test results were not provided from the CEA. The final post-test analysis was performed to predict the test results as accurate as possible by improving the previous modeling of the test. Based on the pre-test analysis and blind test analysis, the modeling for heat structures in the hot pool and cold pool, steel structures in the core, heat loss from roof and vessel, and the flow path at core outlet were reinforced in the final analysis. The results of the final post-test analysis could be characterized into three different phases. In the early phase, the MARS-LMR simulated the heat-up process correctly due to the enhanced heat structure modeling. In the mid phase before the opening of SG casing, the code reproduced the decrease of core outlet temperature successfully. Finally, in the later phase the increase of heat removal by the opening of the SG opening was well predicted with the MARS-LMR code. (authors)

  5. The development of fast neutron reactors in France - from February 1983 to February 1984

    International Nuclear Information System (INIS)

    Benoist, E.; Champeix, L.

    1984-01-01

    The report presents the ''end of life'' tests, the decommissioning and the start of dismantling operations at the Rapsodie reactor. For nuclear power plant Phenix data concerning electricity production, the results of the tests on fuel elements and the occurred accidents are reported. For the nuclear power plant Super Phenix 1 under construction at Creys Malville the results with regard to the reactor core, the fuel elements, the secondary coolant circuits and the auxiliary circuits are presented. The project for the 1500 MWe nuclear power plant Super Phenix 2 is discussed. The research and development activities in the LMFBR field, mainly, technological aspects, reactor core, fuel elements, materials and the test programs concerning especially the safety experiments and sodium-water reactors are summarized in the last part of the report

  6. The PHENIX Drift Chamber Front End Electroncs

    Science.gov (United States)

    Pancake, C.; Velkovska, J.; Pantuev, V.; Fong, D.; Hemmick, T.

    1998-04-01

    The PHENIX Drift Chamber (DC) is designed to operate in the high particle flux environment of the Relativistic Heavy Ion Collider and provide high resolution track measurements. It is segmented into 80 keystones with 160 readout channels each. The Front End Electronics (FEE) developed to meet the demanding operating conditions and the large number of readout channels of the DC will be discussed. It is based on two application specific integrated circuits: the ASD8 and the TMC-PHX1. The ASD8 chip contains 8 channels of bipolar amplifier-shaper-discriminator with 6 ns shaping time and ≈ 20 ns pulse width, which satisfies the two track resolution requirements. The TMC-PHX1 chip is a high-resolution multi-hit Time-to-Digital Converter. The outputs from the ASD8 are digitized in the Time Memory Cell (TMC) every (clock period)/32 or 0.78 ns (at 40 MHz), which gives the intrinsic time resolution of the system. A 256 words deep dual port memory keeps 6.4 μs time history of data at 40 MHz clock. Each DC keystone is supplied with 4 ASD8/TMC boards and one FEM board, which performs the readout of the TMC-PHX1's, buffers and formats the data to be transmitted over the Glink. The slow speed control communication between the FEM and the system is carried out over ARCNET. The full readout chain and the data aquisition system are being tested.

  7. J/ψ suppression and elliptic flow in 200 GeV Au+Au collisions at the mid rapidity region of the PHENIX experiment

    International Nuclear Information System (INIS)

    Atomssa, E.T.

    2008-12-01

    J/Ψ are considered to be one of the key probes of the Quark Gluon Plasma (QGP) formation in heavy ion collisions. Color screening was proposed as a mechanism leading to anomalous suppression beyond normal absorption in nuclear matter if J/Ψs were created in a deconfined medium, providing a direct evidence of deconfinement. The higher energy density that is available at RHIC should create a hotter QGP, and render the suppression signature more significant than in previous measurement performed at CERN SPS. The PHENIX detector is one of the four experiments that were installed at RHIC, with a design that is optimal for the measurement of the J/Ψ meson at forward rapidity in the dimuon decay channel, and at mid rapidity in the dielectron decay channel. Since day one operation in 2001, PHENIX has measured, among many other observables, J/Ψ yields in p+p, d+Au, Cu+Cu and Au+Au collisions in a wide range of energies going from 19 GeV to 200 GeV per pair of nucleons. The work presented here covers the analysis of data taken by the mid rapidity spectrometers of PHENIX in Au+Au collisions at 200 GeV. The nuclear modification factor is measured as a function of centrality, and compared to extrapolations of cold nuclear matter suppression constrained in d+Au collisions at the same energy. Though the suppression seen in the most central collisions goes up to a factor of more than three, given the large errors in the extrapolations, most of it can possibly be accounted for by cold nuclear effects, and the significance of the extra anomalous suppression is small. More strikingly, comparisons to the CERN SPS results and to the suppression measurement at forward rapidity in PHENIX show features that seem to suggest the violation of the intuitive picture of increasing suppression with local energy density. This has led to the speculation that regeneration, a J/Ψ production mechanism by association of uncorrelated c and c-bar quarks, might be at play in central heavy ion

  8. Study of Isospin Correlation in High Energy Heavy Ion Interactions with the RHIC PHENIX. Final Report

    International Nuclear Information System (INIS)

    Takahashi, Y.

    2003-01-01

    This report describes the research work performed under the support of the DOE research grant E-FG02-97ER4108. The work is composed of three parts: (1) Visual analysis and quality control of the Micro Vertex Detector (MVD) of the PHENIX experiments carried out of Brookhaven National Laboratory. (2) Continuation of the data analysis of the EMU05/09/16 experiments for the study of the inclusive particle production spectra and multi-particle correlation. (3) Exploration of a new statistical means to study very high-multiplicity of nuclear-particle ensembles and its perspectives to apply to the higher energy experiments

  9. French fuel cycle strategy and partitioning and transmutation programme

    International Nuclear Information System (INIS)

    Pradel, Ph.

    2007-01-01

    The global energy context pleads in favour of a sustainable development of nuclear energy since the demand for energy will likely increase, whereas resources will tend to get scarcer and the prospect of global warming will drive down the consumption of fossil fuel sources. How we deal with radioactive waste is crucial in this context. The production of nuclear energy in France has been associated, since its inception, with the optimisation of radioactive waste management, including the partitioning and the recycling of recoverable energetic materials. The public's concern regarding long-term waste management led the French government to prepare and pass the Law of December 1991, requesting in particular the study for fifteen years of solutions to minimising even further the quantity and the hazardousness of final waste, via partitioning and transmutation. At the end of these fifteen years of research, it is considered that partitioning techniques which have been validated on real solutions are at disposal. Indeed, aqueous process for separation of minor actinides from the PUREX raffinate has been brought to a point where there is reasonable assurance that industrial deployment can be successful. A key experiment has been the kilogram-scale successful trials in the CEA-Marcoule Atalante facility in 2005 and this result, together with the results obtained in the frame of the successive European projects, constitutes a considerable step forward. For transmutation, CEA has conducted programmes proving the feasibility of the elimination of minor actinides and fission products: fabrication of specific targets and fuels for transmutation tests in the HFR and Phenix reactors, neutronics and technology studies for critical reactors and ADS developments. Scenario studies have also allowed assessing the feasibility, at the level of cycle and fuel facilities, and the efficiency of transmutation in terms of the quantitative reduction of the final waste inventory depending of

  10. Status of the French Research on Partitioning and Transmutation

    International Nuclear Information System (INIS)

    Warin, Dominique

    2007-01-01

    The global energy context pleads in favor of a sustainable development of nuclear energy since the demand for energy will likely increase, whereas resources will tend to get scarcer and the prospect of global warming will drive down the consumption of fossil fuel sources. How we deal with radioactive waste is crucial in this context. The production of nuclear energy in France has been associated, since its inception, with the optimization of radioactive waste management, including the partitioning and the recycling of recoverable energetic materials. The public's concern regarding the long-term waste management made the French Government prepare and pass the December 1991 Law, requesting in particular, the study for fifteen years of solutions for still minimizing the quantity and the hazardousness of final waste, via partitioning and transmutation. At the end of these fifteen years of research, it is considered that partitioning techniques, which have been validated on real solutions, are at disposal. Indeed, aqueous process for separation of minor actinides from the PUREX raffinate has been brought to a point where there is reasonable assurance that industrial deployment can be successful. A key experiment has been the successful kilogram scale trials in the CEA-Marcoule Atalante facility in 2005 and this result, together with the results obtained in the frame of the successive European projects, constitutes a considerable step forward. For transmutation, CEA has conducted programs proving the feasibility of the elimination of minor actinides and fission products: fabrication of specific targets and fuels for transmutation tests in the HFR and Phenix reactors, neutronics and technology studies for critical reactors and ADS developments. Scenario studies have also allowed assessing the feasibility, at the level of cycle and fuel facilities, and the efficiency of transmutation in terms of the quantitative reduction of the final waste inventory depending of the

  11. Behavior of ferritic steels irradiated by fast neutrons

    International Nuclear Information System (INIS)

    Erler, Jean; Maillard, Arlette; Brun, Gilbert; Lehmann, Jeanne; Dupouy, J.-M.

    1979-01-01

    Ferritic steels were irradiated in Rapsodie and Phenix at varying doses. The swelling and irradiation creep characteristics are reported below as are the mechanical characteristics of these materials [fr

  12. Prompt photon measurements with PHENIX's MPC-EX detector

    Science.gov (United States)

    Campbell, Sarah; PHENIX Collaboration

    2013-08-01

    The MPC-EX detector is a Si-W preshower extension to the existing Muon Piston Calorimeter (MPC). The MPC-EX consists of eight layers of alternating W absorber and Si mini-pad sensors. Located at forward rapidity, 3.1 80 GeV, a factor of four improvement over current capabilities. Not only will the MPC-EX strengthen PHENIX's existing forward π0 and jet measurements, it will provide sufficient prompt photon and π0 separation to make a prompt photon measurement possible. Prompt photon yields at high pT, pT > 3 GeV/c, can be statistically extracted using the double ratio method. In transversely polarized p+p collisions, the measurement of the prompt photon single spin asymmetry, AN, will resolve the sign discrepancy between the Sivers and twist-3 extractions of AN. In p+Au collisions, the prompt photon RpAu will quantify the level of gluon saturation in the Au nucleus at low-x, x ~ 10-3, with a projected systematic error band a factor of four smaller than EPS09's current allowable range. The MPC-EX detector will expand our understanding of the gluon nuclear parton distribution functions, providing important information about the initial state of heavy ion collisions, and clarify how the valence parton's transverse momentum and spin correlates to the proton spin.

  13. No hesitation: the gas sector of French industry opts for internationalization

    International Nuclear Information System (INIS)

    Roze, J.

    1997-01-01

    Since French energy reserves are not big enough, additional energy had to be developed abroad or imported. Using skills acquired on fast-growing markets, the manufacturers of transmission pipelines, equipments, and operating devices have also made a determined turn to external markets. In the business strategy of this sector, internationalization has become deeply rooted because the gas services market is worldwide and the gas applications are being developed around the world. French companies in the gas sector, whether dealing with natural gas or with liquefied petroleum gas, have been able to develop the synergy and partnerships, amongst themselves or with foreign companies, necessary to conquer new markets. (J.S.)

  14. Design considerations for economically competitive sodium cooled fast reactors

    International Nuclear Information System (INIS)

    Zhang, Hongbin; Zhao, Haihua; Mousseau, Vincent; Szilard, Ronaldo

    2009-01-01

    The technological viability of sodium cooled fast reactors (SFR) has been established by various experimental and prototype (demonstration) reactors such as EBR-II, FFTF, Phenix, JOYO, BN-600 etc. However, the economic competitiveness of SFR has not been proven yet. The perceived high cost premium of SFRs over LWRs has been the primary impediment to the commercial expansion of SFR technologies. In this paper, cost reduction options are discussed for advanced SFR designs. These include a hybrid loop-pool design to optimize the primary system, multiple reheat and intercooling helium Brayton cycle for the power conversion system and the potential for suppression of intermediate heat transport system. The design options for the fully passive decay heat removal systems are also thoroughly examined. These include direct reactor auxiliary cooling system (DRACS), reactor vessel auxiliary cooling system (RVACS) and the newly proposed pool reactor auxiliary cooling system (PRACS) in the context of the hybrid loop-pool design. (author)

  15. Probing properties of hot and dense QCD matter with heavy flavor in the PHENIX experiment at RHIC

    Directory of Open Access Journals (Sweden)

    Nouicer Rachid

    2015-01-01

    Full Text Available Hadrons carrying heavy quarks, i.e. charm or bottom, are important probes of the hot and dense medium created in relativistic heavy ion collisions. Heavy quarkantiquark pairs are mainly produced in initial hard scattering processes of partons. While some of the produced pairs form bound quarkonia, the vast majority hadronize into particles carrying open heavy flavor. Heavy quark production has been studied by the PHENIX experiment at RHIC via measurements of single leptons from semi-leptonic decays in both the electron channel at mid-rapidity and in the muon channel at forward rapidity. A large suppression and azimuthal anisotropy of single electrons have been observed in Au + Au collisions at 200 GeV. These results suggest a large energy loss and flow of heavy quarks in the hot, dense matter. The PHENIX experiment has also measured J/ψ production at 200 GeV in p + p, d + Au, Cu + Cu and Au + Au collisions, both at mid- and forward-rapidities, and additionally Cu + Au and U + U at forward-rapidities. In the most energetic collisions, more suppression is observed at forward rapidity than at central rapidity. This can be interpreted either as a sign of quark recombination, or as a hint of additional cold nuclear matter effects. The centrality dependence of nuclear modification factor, RAA(pT, for J/ψ in U + U collisions at √sNN = 193 GeV shows a similar trend to the lighter systems, Au + Au and Cu + Cu, at similar energy 200 GeV.

  16. Status of the French research programme for actinides and fission products partitioning and transmutation

    International Nuclear Information System (INIS)

    Warin, D.

    2003-01-01

    The paper focus on separation and transmutation research and development programme and main results over these ten last years. The massive research programme on enhanced separation, conducted by CEA and supported by broad international cooperation, has recently achieved some vital progress. Based on real solutions derived from the La Hague process, the CEA demonstrated the lab-scale feasibility of extracting minor actinides and some fission products (I, Cs and Tc) using an hydrometallurgical process that can be extrapolated on the industrial scale. The CEA also conducted programmes proving the technical feasibility of the elimination of minor actinides and fission products by transmutation: fabrication of specific targets and fuels for transmutation tests in the HFR and Phenix reactors, neutronics and technology studies for ADS developments in order to support the MEGAPIE, TRADE and MYRRHA experiments and the future 100 MW international ADS demonstrator. Scenarios studies aimed at stabilizing the inventory with long-lived radionuclides, plutonium, minor actinides and certain long-lived fission products in different nuclear power plant parks and to verify the feasibility at the level of the cycle facilities and fuels involved in those scenarios. Three French Research Groups CEA-CNRS carry out partitioning (PRACTIS) and transmutation (NOMADE and GEDEON) more basic studies. (author)

  17. Front-end module readout and control electronics for the PHENIX Multiplicity Vertex Detector

    International Nuclear Information System (INIS)

    Ericson, M.N.; Allen, M.D.; Boissevain, J.

    1997-11-01

    Front-end module (FEM) readout and control are implemented as modular, high-density, reprogrammable functions in the PHENIX Multiplicity Vertex Detector. FEM control is performed by the heap manager, an FPGA-based circuit in the FEM unit. Each FEM has 256 channels of front-end electronics, readout, and control, all located on an MCM. Data readout, formatting, and control are performed by the heap manager along with 4 interface units that reside outside the MVD detector cylinder. This paper discusses the application of a generic heap manager and the addition of 4 interface module types to meet the specific control and data readout needs of the MVD. Unit functioning, interfaces, timing, data format, and communication rates will be discussed in detail. In addition, subsystem issues regarding mode control, serial architecture and functions, error handling, and FPGA implementation and programming will be presented

  18. A CMOS variable gain amplifier for PHENIX electromagnetic calorimeter and RICH energy measurements

    Energy Technology Data Exchange (ETDEWEB)

    Wintenberg, A.L.; Simpson, M.L.; Young, G.R. [Oak Ridge National Lab., TN (United States); Palmer, R.L.; Moscone, C.G.; Jackson, R.G. [Tennessee Univ., Knoxville, TN (United States)

    1996-12-31

    A variable gain amplifier (VGA) has been developed equalizing the gains of integrating amplifier channels used with multiple photomultiplier tubes operating from common high-voltage supplies. The PHENIX lead-scintillator electromagnetic calorimeter will operate in that manner, and gain equalization is needed to preserve the dynamic range of the analog memory and ADC following the integrating amplifier. The VGA is also needed for matching energy channel gains prior to forming analog sums for trigger purposes. The gain of the VGA is variable over a 3:1 range using a 5-bit digital control, and the risetime is held between 15 and 23 ns using switched compensation in the VGA. An additional feature is gated baseline restoration. Details of the design and results from several prototype devices fabricated in 1.2-{mu}m Orbit CMOS are presented.

  19. Use of French, Attitudes and Motivations of French Immersion Students.

    Science.gov (United States)

    Van der Keilen, Marguerite

    1995-01-01

    Compares the degree to which pupils in the French immersion and regular English school programs speak French and initiate contact with French people. Attitudes and motivations were significantly more positive, and social tolerance and self-rated competency in French were much higher in the immersion than in English program subjects. (29…

  20. The yawning chasm of French nuclear power

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    The financial problems of the nuclear power industry in France are explained. Cogema, the waste reprocessing company ventured into the French financial futures market and lost money. It is trying to sue its brokers over this disaster. Framatome, the State reactor manufacturer is trying to diversify into aeronautics, electronics and foodstuffs. The electric utility EdF is sliding into debt and, with no price rise allowed, this situation will get worse. Theoretically EdF should be delivering cheap electricity from nuclear power stations. However, French electricity prices are not significantly cheaper than those of Germany and the United Kingdom. The generating capacity will increase greatly over the next few years. The availability of existing plants is also improving. In spite of efforts to export its electricity (about 10% is exported) EdF seem unable to make its extra electricity cheaper and is heavily in debt. The fast breeder programme has also not lived up to expectations due to a sodium leak at Superphenix. (U.K.)

  1. Direct jet reconstruction in p+p and Cu + Cu collisions at PHENIX

    International Nuclear Information System (INIS)

    Lai, Yue Shi

    2011-01-01

    Direct jet reconstruction in heavy ion collisions is an important probe for the in-medium parton energy loss and jet-medium interactions and reconstructed jets provide additional constraints to characterize the underlying mechanisms. However, traditional jet reconstruction algorithms operating in the large soft background at RHIC produce fake jets well above the intrinsic production rate of high-p T hard scattering, thus impeding the detection of the low cross section jet signal at RHIC energies. We developed a jet reconstruction algorithm that locates and reconstructs the jet energy using a Gaussian filter. This algorithm is combined with a fake jet rejection scheme that provides efficient jet reconstruction with acceptable fake rate in a background environment up to the central Au + Au collision at √(s NN )=200GeV. We present results of its application in p+p and Cu + Cu collisions using data from the PHENIX detector, including jet spectrum up to 60 GeV/c, nuclear modification factor, and fragmentation function.

  2. Assembly procedure for the silicon pixel ladder for PHENIX silicon vertex tracker

    International Nuclear Information System (INIS)

    Onuki, Y.; Akiba, Y.; En'yo, H.; Fujiwara, K.; Haki, Y.; Hashimoto, K.; Ichimiya, R.; Kasai, M.; Kawashima, M.; Kurita, K.; Kurosawa, M.; Mannel, E.J.; Nakano, K.; Pak, R.; Sekimoto, M.; Sondheim, W.E.; Taketani, A.; Togawa, M.; Yamamoto, Y.

    2009-01-01

    The silicon vertex tracker (VTX) will be installed in the summer of 2010 to enhance the physics capabilities of the Pioneering High Energy Nuclear Interaction eXperiment (PHENIX) experiment at Brookhaven National Laboratory. The VTX consists of two types of silicon detectors: a pixel detector and a strip detector. The pixel detector consists of 30 pixel ladders placed on the two inner cylindrical layers of the VTX. The ladders are required to be assembled with high precision, however, they should be assembled in both cost and time efficient manner. We have developed an assembly bench for the ladder with several assembly fixtures and a quality assurance (Q/A) system using a 3D measurement machine. We have also developed an assembly procedure for the ladder, including a method for dispensing adhesive uniformly and encapsulation of bonding wires. The developed procedures were adopted in the assembly of the first pixel ladder and satisfy the requirements.

  3. A discriminator with a current-sum multiplicity output for the PHENIX multiplicity vertex detector

    International Nuclear Information System (INIS)

    Smith, R.S.; Kennedy, E.J.; Jackson, R.G.

    1996-01-01

    A current output multiplicity discriminator for use in the front-end electronics (FEE) of the Multiplicity Vertex Detector (MVD) for the PHENIX detector at RHIC has been fabricated in the a 1.2-micro CMOS, n-well process. The discriminator is capable of triggering on input signals ranging from 0.25 MIP to 5 MIP. Frequency response of the discriminator is such that the circuit is capable of generating an output for every bunch crossing (105 ns) of the RHIC collider. Channel-to-channel threshold matching was adjustable to ± 4 mV. One channel of multiplicity discriminator occupied an area of 85 micro x 630 micro and consumed 515 microW from a single 5-V supply. Details of the design and results from prototype device testing are presented

  4. Development and evaluation of the muon trigger detector using a resistive plate chamber

    International Nuclear Information System (INIS)

    Park, Byeong Hyeon

    2010-08-01

    The PHENIX Experiment is the largest of the four experiments that have taken data at the Relativistic Heavy Ion Collider. PHENIX, the Pioneering High Energy Nuclear Interaction experiment, is an exploratory experiment for the investigation of high energy collisions of heavy ions and protons. PHENIX is designed specifically to measure direct probes of the collisions such as electrons, muons, and photons. The primary goal of PHENIX is to discover and study a new state of matter called the Quark-Gluon Plasma. Among many particles, muons coming from W-boson decay gives us key information to analyze the spin of proton. Resistive plate chambers are proposed as a suitable solution as a muon trigger because of their fast response and good time resolution, flexibility in signal readout, robustness and the relatively low cost of production. The RPC detectors for upgrade were assembled and their performances were evaluated. The procedure to make the detectors better was optimized and described in detail in this thesis. The code based on ROOT was written and by using this the performance of the detectors made was evaluated, and all of the modules for north muon arm met the criteria and installation at PHENIX completed in November 2009. As RPC detectors that we made showed fast response, capacity of covering wide area with a resonable price and good spatial resolution, this will give the opportunity for applications,such as diagnosis and customs inspection system

  5. French Teaching Aids.

    Science.gov (United States)

    Miller, J. Dale

    Supplementary teaching materials for French language programs are presented in this text. Primarily intended for secondary school students, the study contains seven units of material. They include: (1) French gestures, (2) teaching the interrogative pronouns, (3) French cuisine, (4) recreational learning games, (5) French-English cognates, (6)…

  6. Electronics cooling of Phenix multiplicity and vertex detector

    International Nuclear Information System (INIS)

    Chen, Z.; Gregory, W.S.

    1996-08-01

    The Multiplicity and Vertex Detector (MVD) uses silicon strip sensors arranged in two concentric barrels around the beam pipe of the PHENIX detector that will be installed at Brookhaven National Laboratory. Each silicon sensor is connected by a flexible kapton cable to its own front-end electronics printed circuit board that is a multi-chip module or MCM. The MCMs are the main heat source in the system. To maintain the MVD at optimized operational status, the maximum temperature of the multi-chip modules must be below 40 C. Using COSMOS/M HSTAR for the Heat Transfer analysis, a finite element model of a typical MCM plate was created to simulate a 9m/s airflow and 9m/s mixed flow composed of 50% helium and 50% air respectively, with convective heat transfer on both sides of the plate. The results using a mixed flow of helium and air show that the average maximum temperature reached by the MCMs is 37.5 C. The maximum temperature which is represented by the hot spots on the MCM is 39.43 C for the helium and air mixture which meets the design temperature requirement 40 C. To maintain the Multiplicity and Vertex Detector at optimized operational status, the configuration of the plenum chamber, the power dissipated by the silicon chips, the fluid flow velocity and comparison on the MCM design parameters will be discussed

  7. Breeding gains of sodium-cooled oxide-fueled fast reactors

    International Nuclear Information System (INIS)

    Mougniot, J.C.; Barre, J.Y.; Clauzon, P.; Ciacometti, C.; Neviere, G.; Ravier, J.; Sichard, B.

    Calculated values are presented for the breeding gains of French fast reactors, and the experimental uncertainties are discussed. The effect of various choices of planning on the breeding gains is next analyzed within the framework of classical concepts. In the final part, a new concept involving ''heterogeneous cores'' with a single enrichment zone is presented. This concept permits a significant improvement in the breeding gain and doubling time of fast reactors. (U.S.)

  8. French Courses

    CERN Multimedia

    2012-01-01

    General and Professional French Courses These courses are open to all persons working on the CERN site, and to their spouses. The next session will take place from 28 January to 5 April 2013. Oral Expression This course is aimed for students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. The next session will take place from 28 January to 5 April 2013. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. The next session will take place from 28 January to 5 April 2013. For registration and further information on the courses, please consult our Web pages or contact Kerstin Fuhrmeister.

  9. The behaviour of ferritic steels under fast neutron irradiation

    International Nuclear Information System (INIS)

    Erler, J.; Maillard, A.; Brun, G.; Lehmann, J.; Dupouy, J.M.

    1979-07-01

    Ferritic steels have been irradiated in Rapsodie and Phenix to doses up to 150 dpa F. The swelling and irradiation creep characteristics and the mechanical properties of these materials are reported. (author)

  10. Wind: French revolutions

    International Nuclear Information System (INIS)

    Jones, C.

    2006-01-01

    Despite having the second best wind resources in Europe after the UK, the wind industry in France lags behind its European counterparts with just 6 W of installed wind capacity per person. The electricity market in France is dominated by the state-owned Electricite de France (EdF) and its nuclear power stations. However, smaller renewable generators are now in theory allowed access to the market and France has transposed the EU renewables directive into national law. The French governement has set a target of generating 10,000 MW of renewable capacity by 2010. The announcement of an increased feed-in tariff and the introduction of 'development zones' (ZDEs) which could allow fast-tracking of planning for wind projects are also expected to boost wind projects. But grid access and adminstrative burdens remain major barriers. In addition, French politicians and local authorities remain committed to nuclear, though encouraged by the European Commission, wind is beginning to gain acceptance; some 325 wind farms (representing 1557 MW of capacity) were approved between February 2004 and January 2005. France is now regarded by the international wind energy sector as a target market. One of France's leading independent wind developers and its only listed wind company, Theolia, is expected to be one of the major beneficiaries of the acceleration of activity in France, though other companies are keen to maximise the opportunities for wind. France currently has only one indigenous manufacturer of wind turbines, but foreign suppliers are winning orders

  11. Future of French refining

    International Nuclear Information System (INIS)

    Calvet, B.

    1993-01-01

    Over recent years, the refining industry has had to grapple with a growing burden of environmental and safety regulations concerning not only its plants and other facilities, but also its end products. At the same time, it has had to bear the effects of the reduction of the special status that used to apply to petroleum, and the consequences of economic freedom, to which we should add, as specifically concerns the French market, the impact of energy policy and the pro-nuclear option. The result is a drop in heavy fuel oil from 36 million tonnes per year in 1973 to 6.3 million in 1992, and in home-heating fuel from 37 to 18 million per year. This fast-moving market is highly competitive. The French market in particular is wide open to imports, but the refining companies are still heavy exporters for those products with high added-value, like lubricants, jet fuel, and lead-free gasolines. The competition has led the refining companies to commit themselves to quality, and to publicize their efforts in this direction. This is why the long-term perspectives for petroleum fuels are still wide open. This is supported by the probable expectation that the goal of economic efficiency is likely to soften the effects of the energy policy, which penalizes petroleum products, in that they have now become competitive again. In the European context, with the challenge of environmental protection and the decline in heavy fuel outlets, French refining has to keep on improving the quality of its products and plants, which means major investments. The industry absolutely must return to a more normal level of profitability, in order to sustain this financial effort, and generate the prosperity of its high-performance plants and equipment. 1 fig., 5 tabs

  12. Design and performance of beam test electronics for the PHENIX multiplicity vertex detector

    International Nuclear Information System (INIS)

    Britton, C.L. Jr.; Bryan, W.L.; Emery, M.S.

    1996-01-01

    The system architecture and test results of the custom circuits and beam test system for the Multiplicity-Vertex Detector (MVD) for the PHENIX detector collaboration at the Relativistic Heavy Ion Collider (RHIC) are presented in this paper. The final detector per-channel signal processing chain will consist of a preamplifier-gain stage, a current-mode summed multiplicity discriminator, a 64-deep analog memory (simultaneous read-write), a post-memory analog correlator, and a 10-bit 5 μs ADC. The Heap Manager provides all timing control, data buffering, and data formatting for a single 256-channel multi-chip module (MCM). Each chip set is partitioned into 32-channel sets. Beam test (16-cell deep memory) performance for the various blocks will be presented as well as the ionizing radiation damage performance of the 1.2 μ n-well CMOS process used for preamplifier fabrication

  13. Phenix City 10 x 20 NTMS area, Alabama and Georgia: data report (abbreviated)

    International Nuclear Information System (INIS)

    Bennett, C.B.

    1981-08-01

    This abbreviated data report presents results of ground water, surface water, and stream sediment reconnaissance in the National Topographic Map Series (NTMS) Phenix City 1 0 x 2 0 quadrangle. Surface sediment samples were collected at 1153 sites. Ground water samples were collected at 949 sites. Neutron activation analysis (NAA) results are given for uranium and 16 other elements in sediments, for uranium and 8 other elements in ground water, and for uranium and 9 other elements in surface water. Field measurements and observations are reported for each site. Analytical data and field measurments are presented in tables and maps. Uranium concentrations above detection limits in the sediment samples ranged from 1.0 to 171, with a mean of 10.6 ppM. Uranium concentrations detected in the ground water samples ranged from 0.006 to 23.1 ppB, with a mean of 0.28 ppB

  14. Status and development programme of the fast breeder reactor system in the Federal Republic of Germany

    International Nuclear Information System (INIS)

    Daeunert, U.; Kessler, G.

    1977-01-01

    The Federal Republic of Germany depends on imports of raw materials for energy purposes, and special importance is therefore given to nuclear energy for reasons of energy policy. Against the background of a nuclear power station capacity amounting to 24,000MW(e) in 1976 (power stations being either on order, under construction or actually in operation), the fast breeder reactor (FBR) is outstandingly significant in the Federal Republic for the economic use both of the uranium and the plutonium accumulating in light-water reactors (LWRs). Work in this sector started in the FRG in 1960. Important stages in development were: the initial activities on the plutonium critical SNEAK at Karlsruhe; successful operation of the KNK 20-MW(e) experimental reactor (sodium-cooled) with the KNK II (plutonium core) follow-up stage; costruction of the 300-MW(e) FBR prototype nuclear power station at Kalkar; and initial planning carried out for a 1300-MW(e) FBR demonstration nuclear power station. A viable infrastructure for safety assessment must go hand in hand with the development of new reactor systems. Prototype reactors in the FRG are therefore already subjected to the same strict licensing procedures under nuclear legislation as are commercial nuclear power stations. Several years' practical experience have shown that this was the right approach. It was recognized in the FRG early on that major long-term technological projects could no longer be implemented by unaided single nations. The SNR-300 FBR prototype project combines the efforts of the governments, power supply companies, reactor manufacturers and nuclear research centres of the FRG, Belgium and the Netherlands. The agreement signed in 1971 by the Rheinisch-Westfaelische Elektrizitaetswerke AG (FRG), Ente Nazionale per l'Energia Elettrica (Italy) and Electricite de France (France) power supply companies on the joint construction of the Super-Phenix and SNR-2 FBR demonstration nuclear power stations, and the German-French

  15. French Foodscapes

    DEFF Research Database (Denmark)

    Hedegaard, Liselotte

    By exploring how local and regional products and uses of food interact with the changes in the French cuisine over time, this paper seeks to retrace the history of the French meal through meanings of place and time, terroir and savoir-faire. The study will be based on sources from early modern/modern history...... the destructuralisation of eating habits have been raised since the 1980s, but numerous studies emphasise that the traditional French meal is still playing an important role in everyday life in France. Despite regional variations, the general view of the structure of a traditional French meal as based on the succession...... of flavours and the accordance with wines is widespread. Such a comprehension means giving precedence to gastronomic reasons for determining the order of dishes. However, the French meal has not always been composed in the way it is today and the reasons for the composition have not always been gastronomic...

  16. French courses

    CERN Document Server

    HR Department

    2012-01-01

    General and Professional French Courses The next session will take place from 2nd May to 6th July 2012. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages or contact Kerstin Fuhrmeister.   Oral Expression This course is aimed for students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. Suitable candidates should contact Kerstin Fuhrmeister (70896) in order to arrange an appointment for a test. The next session will take place from 2nd May to 6th July 2012.   Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. Suitable candidates should contact Kerstin Fuhrmeister (70896) in order to arrange an appointment for a test. The next session will take place from 2nd May to ...

  17. French courses

    CERN Document Server

    2013-01-01

    General and Professional French Courses The next session will take place from 29 April to 5 July 2013. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages or contact Kerstin Fuhrmeister (kerstin.fuhrmeister@cern.ch). Oral Expression This course is aimed for students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. Suitable candidates should contact Kerstin Fuhrmeister (70896) in order to arrange an appointment for a test. The next session will take place from 29 April to 5 July 2013. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. Suitable candidates should contact Kerstin Fuhrmeister (70896) in order to arrange an appointment for a test. The next session will take place from 29 April to 5 July...

  18. French Society Abroad: The Popularization of French Dance throughout Europe, 1600-1750

    Directory of Open Access Journals (Sweden)

    Adam Paul Rinehart

    2017-09-01

    Full Text Available This paper explores the dissemination of French dance, dance notation, and dance music throughout Europe, and it explains the reasons why French culture had such an influence on other European societies from 1600-1750. First, the paper seeks to prove that King Louis XIV played a significant role in the outpour of French dance and the arts. Next, the paper discusses prominent French writers of dance notation who influenced the spread of French dance literature and training throughout Europe. Finally, the paper delineates European composers and their involvement in the development and production of French dance music. Using academic, peer-reviewed journal articles, books, and other scholarly sources, this paper seeks to accurately present the information in an orderly fashion. The paper contains visual evidence of dance and music notation to assist the reader in understanding the subject matter. Additionally, theories of contemporary authors as well as authors from the time period are discussed to present concrete evidence. The two main types of dance discussed in the paper are ballroom and court dances, which were prominent within the French royal court. One major finding of the research is the fact that French court and ballroom dances were specifically designed to communicate the power and prestige of King Louis XIV; consequently, other European countries were influenced to strive for similar prestige. Another finding is that many forms of French dance notation were translated and published in other countries, which increased the use of French dance throughout Europe. Musically, European composers such as Handel and Mozart included elements of French dance music in their compositions, and thus played a significant role in prevalence of French dance music throughout Europe. Overall, this paper proves that French dance received wide recognition due to political influence, availability of dance notation, and the involvement of prominent composers.

  19. 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

  20. What would Batman eat?: priming children to make healthier fast food choices.

    Science.gov (United States)

    Wansink, B; Shimizu, M; Camps, G

    2012-04-01

    Fast food patronage is a frequent reality for many children and their parents. Although there are increasingly healthier alternatives for popular menu items (apple slices instead of French fries), they are infrequently selected. We investigated whether either of two priming tactics - the priming of a role model's food choices or the priming of healthy foods - could influence children to make healthier fast food choices. In the priming model condition, 22 children (ranging in age from 6 to 12 years) were presented with 12 photos of 6 admirable and 6 less admirable models and asked, 'Would this person order apple fries or French fries?' In the health prime condition, the same children were shown 12 photos of 6 healthy foods and 6 less healthy foods and asked to indicate if each food was healthy or unhealthy. When children were asked what various admirable people - such as Batman or Spiderman - would eat, 45% chose apple slices over French fries, which was higher than the health prime (P < 0.001) or the control condition (P < 0.001). Advising a parent to ask their child 'What would Batman (or another admired character or person) eat?' might be an easy step to take in what could be a healthier fast food world. © 2012 The Authors. Pediatric Obesity © 2012 International Association for the Study of Obesity.

  1. Fabrication technology and characteristics of AmO2-MgO cercer materials for transmutation

    International Nuclear Information System (INIS)

    Croixmarie, Y.; Mocellin, A.; Warin, D.

    2000-01-01

    This paper deals with the fabrication technology and the physico-chemical properties of target materials prepared for the ECRIX experiment in the French PHENIX reactor. The ECRIX target materials consist of pellets made of a ceramic-ceramic type composite in which particles of americium oxide are microdispersed in an inert matrix of magnesium oxide

  2. French grammar for dummies

    CERN Document Server

    Mazet, Veronique

    2013-01-01

    The easy way to master French grammar French Grammar For Dummies is a logical extension and complement to the successful language learning book, French For Dummies. In plain English, it teaches you the grammatical rules of the French language, including parts of speech, sentence construction, pronouns, adjectives, punctuation, stress and verb tenses, and moods. Throughout the book, you get plenty of practice opportunities to help you on your goal of mastering basic French grammar and usage. Grasp the grammatical rules of French including parts of speech, sentenc

  3. Comparing Written Competency in Core French and French Immersion Graduates

    Science.gov (United States)

    Lappin-Fortin, Kerry

    2014-01-01

    Few studies have compared the written competency of French immersion students and their core French peers, and research on these learners at a postsecondary level is even scarcer. My corpus consists of writing samples from 255 students from both backgrounds beginning a university course in French language. The writing proficiency of core French…

  4. A CMOS Integrating Amplifier for the PHENIX Ring Imaging Cherenkov detector

    International Nuclear Information System (INIS)

    Wintenberg, A.L.; Jones, J.P. Jr.; Young, G.R.; Moscone, C.G.

    1997-11-01

    A CMOS integrating amplifier has been developed for use in the PHENIX Ring Imaging Cherenkov (RICH) detector. The amplifier, consisting of a charge-integrating amplifier followed by a variable gain amplifier (VGA), is an element of a photon measurement system comprising a photomultiplier tube, a wideband, gain of 10 amplifier, the integrating amplifier, and an analog memory followed by an ADC and double correlated sampling implemented in software. The integrating amplifier is designed for a nominal full scale input of 160 pC with a gain of 20 mV/pC and a dynamic range of 1000:1. The VGA is used for equalizing gains prior to forming analog sums for trigger purposes. The gain of the VGA is variable over a 3:1 range using a 5 bits digital control, and the risetime is held to approximately 20 ns using switched compensation in the VGA. Details of the design and results from several prototype devices fabricated in 1.2 microm Orbit CMOS are presented. A complete noise analysis of the integrating amplifier and the correlated sampling process is included as well as a comparison of calculated, simulated and measured results

  5. A CMOS Integrating Amplifier for the PHENIX Ring Imaging Cherenkov detector

    Energy Technology Data Exchange (ETDEWEB)

    Wintenberg, A.L.; Jones, J.P. Jr.; Young, G.R. [Oak Ridge National Lab., TN (United States); Moscone, C.G. [Tennessee Univ., Knoxville, TN (United States)

    1997-11-01

    A CMOS integrating amplifier has been developed for use in the PHENIX Ring Imaging Cherenkov (RICH) detector. The amplifier, consisting of a charge-integrating amplifier followed by a variable gain amplifier (VGA), is an element of a photon measurement system comprising a photomultiplier tube, a wideband, gain of 10 amplifier, the integrating amplifier, and an analog memory followed by an ADC and double correlated sampling implemented in software. The integrating amplifier is designed for a nominal full scale input of 160 pC with a gain of 20 mV/pC and a dynamic range of 1000:1. The VGA is used for equalizing gains prior to forming analog sums for trigger purposes. The gain of the VGA is variable over a 3:1 range using a 5 bits digital control, and the risetime is held to approximately 20 ns using switched compensation in the VGA. Details of the design and results from several prototype devices fabricated in 1.2 {micro}m Orbit CMOS are presented. A complete noise analysis of the integrating amplifier and the correlated sampling process is included as well as a comparison of calculated, simulated and measured results.

  6. The French experience

    CERN Document Server

    Bougard, Marie-Thérèse

    2003-01-01

    Developed for beginners, The French Experience 1 course book is designed to accompany the French Experience 1 CDs (9780563472582) but can also be used on its own to develop your reading and writing skills. You’ll gain valuable insights into French culture too.

  7. Code system for fast reactor neutronics analysis

    International Nuclear Information System (INIS)

    Nakagawa, Masayuki; Abe, Junji; Sato, Wakaei.

    1983-04-01

    A code system for analysis of fast reactor neutronics has been developed for the purpose of handy use and error reduction. The JOINT code produces the input data file to be used in the neutronics calculation code and also prepares the cross section library file with an assigned format. The effective cross sections are saved in the PDS file with an unified format. At the present stage, this code system includes the following codes; SLAROM, ESELEM5, EXPANDA-G for the production of effective cross sections and CITATION-FBR, ANISN-JR, TWOTRAN2, PHENIX, 3DB, MORSE, CIPER and SNPERT. In the course of the development, some utility programs and service programs have been additionaly developed. These are used for access of PDS file, edit of the cross sections and graphic display. Included in this report are a description of input data format of the JOINT and other programs, and of the function of each subroutine and utility programs. The usage of PDS file is also explained. In Appendix A, the input formats are described for the revised version of the CIPER code. (author)

  8. Study of the efficiency of the anti-convective thermal barrier of the Super-Phenix vessels inter space

    International Nuclear Information System (INIS)

    Durin, M.; Mejane, A.

    1983-08-01

    In the LMFBR Phenix reactor, the junction between the primary vessel and the roof slab is a region of large thermal gradients. In order to limit the gradient in the primary vessel, a thermal barrier has been installed between the primary and the safety vessel. The purpose of this barrier is to prevent the penetration of hot gas in the upper part of the vessels inter space. Experimental results have been obtained on a full scale model representing a 25 0 vessel sector of the reactor. Different geometrical configurations have been tested for a large range of boundary condition: - perfectly tight barrier - no thermal barrier; - simulation of leakages on the barrier [fr

  9. Eleventh annual meeting, Bologna, Italy, 17-20 April 1978. Summary report. Part III

    International Nuclear Information System (INIS)

    1978-09-01

    The Summary Report - Part III of the Eleventh Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercialization LMFBRs according to national plans, mostly related to technology of fuel fabrication, PHENIX fuel pins testing, heterogeneous cores, in service inspection of fuel elements, regulations and licensing, and related OECD activities. Most of the discussions were related to the existing reactors: BR-10, BN-600, BN-350, BN-1600, RAPSODIE and PHENIX

  10. Eleventh annual meeting, Bologna, Italy, 17-20 April 1978. Summary report. Part III

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-09-01

    The Summary Report - Part III of the Eleventh Annual Meeting of the IAEA International Working Group on Fast Reactors - contains the discussions on the commercialization LMFBRs according to national plans, mostly related to technology of fuel fabrication, PHENIX fuel pins testing, heterogeneous cores, in service inspection of fuel elements, regulations and licensing, and related OECD activities. Most of the discussions were related to the existing reactors: BR-10, BN-600, BN-350, BN-1600, RAPSODIE and PHENIX.

  11. Examination in hot laboratories of irradiated fuels from fast reactors

    International Nuclear Information System (INIS)

    Clottes, G.; Peray, R.; Ratier, J.L.

    1980-05-01

    Low irradiation rate examinations were carried out soon after the Rapsodie, Rapsodie Fortissimo and Phenix reactors were started up for the first time in order to check the level of maximum temperatures reached and the radial migration of oxygen and plutonium and to assess the movements of fuels inside the cladding. The other examinations were effected at a high specific burnup in order to defines the limit specific burnup securing the integrity of the fuel pin claddings (distortion, ruptures and possible consequences). The examinations carried out so far on fuel elements coming from Phenix or Rapsodie have allowed good fuel surveillance to be undertaken and the acquisition of a large number of data, thanks to which the fuel characteristics of future reactors of the system have been developed [fr

  12. Fast food: unfriendly and unhealthy.

    Science.gov (United States)

    Stender, S; Dyerberg, J; Astrup, A

    2007-06-01

    Although nutrition experts might be able to navigate the menus of fast-food restaurant chains, and based on the nutritional information, compose apparently 'healthy' meals, there are still many reasons why frequent fast-food consumption at most chains is unhealthy and contributes to weight gain, obesity, type 2 diabetes and coronary artery disease. Fast food generally has a high-energy density, which, together with large portion sizes, induces over consumption of calories. In addition, we have found it to be a myth that the typical fast-food meal is the same worldwide. Chemical analyses of 74 samples of fast-food menus consisting of French fries and fried chicken (nuggets/hot wings) bought in McDonalds and KFC outlets in 35 countries in 2005-2006 showed that the total fat content of the same menu varies from 41 to 65 g at McDonalds and from 42 to 74 g at KFC. In addition, fast food from major chains in most countries still contains unacceptably high levels of industrially produced trans-fatty acids (IP-TFA). IP-TFA have powerful biological effects and may contribute to increased weight gain, abdominal obesity, type 2 diabetes and coronary artery disease. The food quality and portion size need to be improved before it is safe to eat frequently at most fast-food chains.

  13. Essential French grammar

    CERN Document Server

    Thacker, Mike

    2014-01-01

    Essential French Grammar is an innovative reference grammar and workbook for intermediate and advanced undergraduate students of French (CEFR levels B2 to C1). Its clear explanations of grammar are supported by contemporary examples and lively cartoon drawings.  Each chapter contains: * real-life language examples in French, with English translations * a 'key points' box and tables that summarise grammar concepts * a variety of exercises to reinforce learning * a contemporary primary source or literary extract to illustrate grammar in context. To aid your understanding, this book also contains a glossary of grammatical terms in French and English, useful verb tables and a key to the exercises. Together, these features all help you to grasp complex points of grammar and develop your French language skills.

  14. Fast breeder reactors

    International Nuclear Information System (INIS)

    Ollier, J.L.

    1987-01-01

    The first industrial-scale fast breeder reactor (FBR) is the Superphenix I at Crays-Melville. It was designed and built by Novatome, a French company, and Ansaldo, an Italian company. The advantages of FBRs are summarized. The status of Superphenix and the testing schedule is given. The stages in its power escalation in 1986 are given. The article is optimistic about the future for FBRs and expects FBRs to take over from PWRs at the beginning of the 21st Century. To achieve economic viability, European financial cooperation for the research and development programme is advocated. (UK)

  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. Development and Evaluation of the Muon Trigger Detector Using a Resistive Plate Chamber

    International Nuclear Information System (INIS)

    Park, Byeong Hyeon; Kim, Yong Kyun; Kang, Jeong Soo; Kim, Young Jin; Choi, Ihn Jea; Kim, Chong; Hong, Byung Sik

    2011-01-01

    The PHENIX Experiment is the largest of the four experiments that have taken data at the Relativistic Heavy Ion Collider. PHENIX, the Pioneering High Energy Nuclear Interaction eXperiment, is designed specifically to measure direct probes of the collisions such as electrons, muons, and photons. The primary goal of PHENIX is to discover and study a new state of matter called the Quark-Gluon Plasma. Among many particles, muons coming from W-boson decay gives us key information to analyze the spin of proton. Resistive plate chambers are proposed as a suitable solution as a muon trigger because of their fast response and good time resolution, flexibility in signal readout, robustness and the relatively low cost of production. The RPC detectors for upgrade were assembled and their performances were evaluated. The procedure to make the detectors better was optimized and described in detail in this thesis. The code based on ROOT was written and by using this the performance of the detectors made was evaluated, and all of the modules for north muon arm met the criteria and installation at PHENIX completed in November 2009. As RPC detectors that we made showed fast response, capacity of covering wide area with a resonable price and good spatial resolution, this will give the opportunity for applications, such as diagnosis and customs inspection system

  17. 500 French verbs for dummies

    CERN Document Server

    Erotopoulos

    2013-01-01

    Vexed by French verbs? Fear no more! In 500 French Verbs For Dummies, beginning French language learners can find a quick reference for verbs in the basic present tenses. More advanced French speakers can utilize this book to learn more complex verb tenses and conjugations as well as advanced verbs with irregular endings. One page for each of the 500 most commonly used verbs in the French language -alphabetically arranged and numbered for easy referenceSpecial designation of the 50 most essential French verbsA summary of basic French grammar that incl

  18. Portion sizes and obesity: responses of fast-food companies.

    Science.gov (United States)

    Young, Lisa R; Nestle, Marion

    2007-07-01

    Because the sizes of food portions, especially of fast food, have increased in parallel with rising rates of overweight, health authorities have called on fast-food chains to decrease the sizes of menu items. From 2002 to 2006, we examined responses of fast-food chains to such calls by determining the current sizes of sodas, French fries, and hamburgers at three leading chains and comparing them to sizes observed in 1998 and 2002. Although McDonald's recently phased out its largest offerings, current items are similar to 1998 sizes and greatly exceed those offered when the company opened in 1955. Burger King and Wendy's have increased portion sizes, even while health authorities are calling for portion size reductions. Fast-food portions in the United States are larger than in Europe. These observations suggest that voluntary efforts by fast-food companies to reduce portion sizes are unlikely to be effective, and that policy approaches are needed to reduce energy intake from fast food.

  19. French grammar and usage

    CERN Document Server

    Hawkins, Roger

    2015-01-01

    Long trusted as the most comprehensive, up-to-date and user-friendly grammar available, French Grammar and Usage is a complete guide to French as it is written and spoken today. It includes clear descriptions of all the main grammatical phenomena of French, and their use, illustrated by numerous examples taken from contemporary French, and distinguishes the most common forms of usage, both formal and informal.Key features include:Comprehensive content, covering all the major structures of contemporary French User-friendly organisation offering easy-to-find sections with cross-referencing and i

  20. French Literature Abroad: Towards an Alternative History of French Literature

    Directory of Open Access Journals (Sweden)

    Simon Gaunt

    2015-07-01

    Full Text Available What would a history of medieval literature in French that is not focused on France and Paris look like? Taking as its starting point the key role played in the development of textual culture in French by geographical regions that are either at the periphery of French-speaking areas, or alternatively completely outside them, this article offers three case studies: first of a text composed in mid-twelfth century England; then of one from early thirteenth-century Flanders; and finally from late thirteenth-century Italy. What difference does it make if we do not read these texts, and the language in which they are written, in relation to French norms, but rather look at their cultural significance both at their point of production, and then in transmission? A picture emerges of a literary culture in French that is mobile and cosmopolitan, one that cannot be tied to the teleology of an emerging national identity, and one that is a bricolage of a range of influences that are moving towards France as well as being exported from it. French itself functions as a supralocal written language (even when it has specific local features and therefore may function more like Latin than a local vernacular.

  1. The fast breeder reactor Rapsodie (1962)

    International Nuclear Information System (INIS)

    Vautrey, L.; Zaleski, C.P.

    1962-01-01

    In this report, the authors describe the Rapsodie project, the French fast breeder reactor, as it stands at construction actual start-up. The paper provides informations about: the principal neutronic and thermal characteristics, the reactor and its cooling circuits, the main handling devices of radioactive or contaminated assemblies, the principles and means governing reactor operation, the purposes and locations of miscellaneous buildings. Rapsodie is expected to be critical by 1964. (authors) [fr

  2. Invitation Refusals in Cameroon French and Hexagonal French

    Science.gov (United States)

    Farenkia, Bernard Mulo

    2015-01-01

    Descriptions of regional pragmatic variation in French are lacking to date the focus has been on a limited range of speech acts, including apologies, requests, compliments and responses to compliments. The present paper, a systematic analysis of invitation refusals across regional varieties of French, is designed to add to the research on…

  3. Unforgettable French Memory Tricks to Help You Learn and Remember French Grammar

    CERN Document Server

    Rice-Jones, Maria

    2010-01-01

    Unforgettable French uses memory tricks to teach and reinforce major points of rench grammar from the basics up to high school level, to learners of all ages. It may be used: by anyone who wishes to gain confidence in speaking French, as a evision aid, to consolidate the learner's grasp of grammatical points, to complement whatever French scheme you are using, and by French teachers at all levels, from elementary school through to adult. These tried-and-tested memory tricks help to explain "tri

  4. French Training

    CERN Multimedia

    Françoise Benz

    2003-01-01

    General and Professional French Courses The next session will take place: from 13 October to 19 December 2003. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages or contact Mrs. Fontbonne: Tel. 72844. Writing Professional Documents in French This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF (for 8 students) For further information and registration, please consult our Web pages or contact Mrs. Fontbonne: Tel. 72844. Language Training Françoise Benz Tel.73127 language.training@cern.ch

  5. Fast reactor versions: elements of choice

    International Nuclear Information System (INIS)

    Tassart, J.; Zerbib, J.C.

    1984-01-01

    This paper has the objective of explaining in detail the economical, political, social and technical elements on which the CFDT (French Trade Union) bases its opposition to the commercial development of the version of fast reactors. An examination of the different choices which were investigated does not point to any legitimate grounds for this choice. What has to be done is to present the facts which enable the greatest possible number of workers or civilians to take up a position on the choices concerning them. A technical comparison of the fast neutron reactor with those operating at present is put forward (France and United Kingdom). It covers the different radioactive waste products and the results of the individual and collective monitoring of the workmen [fr

  6. Interactive effects of reward sensitivity and residential fast-food restaurant exposure on fast-food consumption.

    Science.gov (United States)

    Paquet, Catherine; Daniel, Mark; Knäuper, Bärbel; Gauvin, Lise; Kestens, Yan; Dubé, Laurette

    2010-03-01

    Local fast-food environments have been increasingly linked to obesity and related outcomes. Individuals who are more sensitive to reward-related cues might be more responsive to such environments. This study aimed to assess the moderating role of sensitivity to reward on the relation between residential fast-food restaurant exposure and fast-food consumption. Four hundred fifteen individuals (49.6% men; mean age: 34.7 y) were sampled from 7 Montreal census tracts stratified by socioeconomic status and French/English language. The frequency of fast-food restaurant visits in the previous week was self-reported. Sensitivity to reward was self-reported by using the Behavioral Activation System (BAS) scale. Fast-food restaurant exposure within 500 m of the participants' residence was determined by using a Geographic Information System. Main and interactive effects of the BAS and fast-food restaurant exposure on fast-food consumption were tested with logistic regression models that accounted for clustering of observations and participants' age, sex, education, and household income. Regression results showed a significant interaction between BAS and fast-food restaurant exposure (P food restaurant exposure and consumption was positive for the highest tertile (odds ratio: 1.49; 95% CI: 1.20, 1.84; P < 0.001) but null for the intermediate (odds ratio: 1.03; 95% CI: 0.80, 1.34; P = 0.81) and lowest (odds ratio: 0.84; 95% CI: 0.51, 1.37; P = 0.49) tertiles. Reward-sensitive individuals may be more responsive to unhealthful cues in their immediate environment.

  7. Steam generators of Phenix: Measurement of the hydrogen concentration in sodium for detecting water leaks in the steam generator tubes; Generateurs de vapeur de Phenix-mesure de la concentration d'hydrogene du sodium pour la surveillance de l'etancheite des tubes d'eau-vapeur

    Energy Technology Data Exchange (ETDEWEB)

    Cambillard, E; Lacroix, A; Langlois, J; Viala, J

    1975-07-01

    The Phenix secondary circuits are provided with measurement systems of hydrogen concentration in sodium, that allow for the detection of possible water leaks in steam generators and the location of a faulty module. A measurement device consists of : a detector with nickel membranes of 0, 3 mm wall thickness, an ion pump with a 200 l/s flow rate, a quadrupole mass spectrometer and a calibrated hydrogen leak. The temperature correction is made automatically. The main tests carried out on the leak detection systems are reported. Since the first system operation (October 24, 1973), the measurements allowed us to obtain the hydrogen diffusion rates through the steam generator tube walls. (author)

  8. French PWR Safety Philosophy

    International Nuclear Information System (INIS)

    Conte, M. M.

    1986-01-01

    The first 900 MWe units, built under the American Westinghouse licence and with reference to the U. S. regulation, were followed by 28 standardized units, C P1 and C P2 series. Increasing knowledge and lessons learned from starting and operating experience of French nuclear power plants, completed by the experience learned from the operation of foreign reactors, has contributed to the improvement of French PWR design and safety philosophy. As early as 1976, this experience was taken into account by French Safety organisms to discuss, with Electricite de France, the safety options for the planned 1300 MWe units, P4 and P4 series. In 1983, the new reactor scheduled, Ni4 series 1400 MWe, is a totally French design which satisfies the French regulations and other French standards and codes. Based on a deterministic approach, the French safety analysis was progressively completed by a probabilistic approach each of them having possibilities and limits. Increasing knowledge and lessons learned from operating experience have contributed to the French safety philosophy improvement. The methodology now applied to safety evaluation develops a new facet of the in depth defense concept by taking highly unlikely events into consideration, by developing the search of safety consistency of the design, and by completing the deterministic approach by the probabilistic one

  9. French Dictionaries. Series: Specialised Bibliographies.

    Science.gov (United States)

    Klaar, R. M.

    This is a list of French monolingual, French-English and English-French dictionaries available in December 1975. Dictionaries of etymology, phonetics, place names, proper names, and slang are included, as well as dictionaries for children and dictionaries of Belgian, Canadian, and Swiss French. Most other specialized dictionaries, encyclopedias,…

  10. French development program on fuel cycle

    International Nuclear Information System (INIS)

    Viala, M.; Bourgeois, M.

    1991-01-01

    The need to close the fuel cycle of fast reactors makes the development of the cycle installations (fuel fabrication, irradiated assembly conditioning before reprocessing, reprocessing and waste management) especially independent with the development of the reactor. French experience with the integrated cycle over a period of about 25 years, the tonnage of fuels fabricated (more than 100 t of mixed oxides) for the Rapsodie, Phoenix and SuperPhoenix reactors, and the tonnage of reprocessed fuel (nearly 30 t of plutonium fuel) demonstrate the control of the cycle operations. The capacities of the cycle installations in existence and under construction are largely adequate for presents needs, even including a new European EFR reactor. They include the Cadarache fuel fabrication complex, the La Hague UP2-800 reprocessing plant, and the Marcoule pilot facility. Short- and medium-term R and D programs are connected with fuel developments, with the primary objective of very high burnups. For the longer term and for a specific plant to reprocess fast reactor fuels, the programs could concern new fabrication and reprocessing systems and the study of the consequences of the reduction in fuel out-of-core time

  11. Steam generators of Phenix: Measurement of the hydrogen concentration in sodium for detecting water leaks in the steam generator tubes

    International Nuclear Information System (INIS)

    Cambillard, E.; Lacroix, A.; Langlois, J.; Viala, J.

    1975-01-01

    The Phenix secondary circuits are provided with measurement systems of hydrogen concentration in sodium, that allow for the detection of possible water leaks in steam generators and the location of a faulty module. A measurement device consists of : a detector with nickel membranes of 0, 3 mm wall thickness, an ion pump with a 200 l/s flow rate, a quadrupole mass spectrometer and a calibrated hydrogen leak. The temperature correction is made automatically. The main tests carried out on the leak detection systems are reported. Since the first system operation (October 24, 1973), the measurements allowed us to obtain the hydrogen diffusion rates through the steam generator tube walls. (author)

  12. A comprehensive French grammar

    CERN Document Server

    Price, Glanville

    2013-01-01

    Characterized by clear and accessible explanations, numerous examples and sample sentences, a new section on register and tone, and useful appendices covering topics including age and time, A Comprehensive French Grammar, Sixth Edition is an indispensable tool for advanced students of French language and literature.A revised edition of this established, bestselling French grammarIncludes a new section on register and medium and offers expanded treatment of French punctuationFeatures numerous examples and sample sentences, and useful appendices covering topics including age, time, and dimension

  13. Progress in the development of the neutron flux monitoring system of the French GEN-IV SFR: simulations and experimental validations [ANIMMA--2015-IO-392

    Energy Technology Data Exchange (ETDEWEB)

    Jammes, C.; Filliatre, P.; Izarra, G. de [CEA, DEN, Cadarache, Reactor Studies Department, 13108 Saint-Paul-lez-Durance (France); Elter, Zs. [CEA, DEN, Cadarache, Reactor Studies Department, 13108 Saint-Paul-lez-Durance (France); Chalmers University of Technology, Department of Applied Physics, Division of Nuclear Engineering, SE-412 96 Goeteborg (Sweden); Verma, V. [CEA, DEN, Cadarache, Reactor Studies Department, 13108 Saint-Paul-lez-Durance (France); Uppsala University, Division of Applied Nuclear Physics, Box 516, SE-75120 Uppsala (Sweden); Hamrita, H.; Bakkali, M. [CEA, DRT, LIST, Metrology, Instrumentation and Information Department, Saclay, 91191 Gif-sur-Yvette (France); Chapoutier, N.; Scholer, A.C.; Verrier, D. [AREVA NP, 10 rue Juliette Recamier F-69456 Lyon (France); Hellesen, C.; Jacobsson, S. [Uppsala University, Division of Applied Nuclear Physics, Box 516, SE-75120 Uppsala (Sweden); Pazsit, I. [Chalmers University of Technology, Department of Applied Physics, Division of Nuclear Engineering, SE-412 96 Goeteborg (Sweden); Cantonnet, B.; Nappe, J.C. [PHOTONIS France, Nuclear Instrumentation, 19100 Brive-la-Gaillarde (France); Molinie, P.; Dessante, P.; Hanna, R.; Kirkpatrick, M.; Odic, E. [Supelec, Energy Department, 3 rue Joliot-Curie, 91191 Gif-sur-Yvette (France)

    2015-07-01

    France has a long experience of about 50 years in designing, building and operating sodium-cooled fast reactors (SFR) such as RAPSODIE, PHENIX and SUPER PHENIX. Fast reactors feature the double capability of reducing nuclear waste and saving nuclear energy resources by burning actinides. Since this reactor type is one of those selected by the Generation IV International Forum, the French government asked, in the year 2006, CEA, namely the French Alternative Energies and Atomic Energy Commission, to lead the development of an innovative GEN-IV nuclear- fission power demonstrator. The major objective is to improve the safety and availability of an SFR. The neutron flux monitoring (NFM) system of any reactor must, in any situation, permit both reactivity control and power level monitoring from startup to full power. It also has to monitor possible changes in neutron flux distribution within the core region in order to prevent any local melting accident. The neutron detectors will have to be installed inside the reactor vessel because locations outside the vessel will suffer from severe disadvantages; radially the neutron shield that is also contained in the reactor vessel will cause unacceptable losses in neutron flux; below the core the presence of a core-catcher prevents from inserting neutron guides; and above the core the distance is too large to obtain decent neutron signals outside the vessel. Another important point is to limit the number of detectors placed in the vessel in order to alleviate their installation into the vessel. In this paper, we show that the architecture of the NFM system will rely on high-temperature fission chambers (HTFC) featuring wide-range flux monitoring capability. The definition of such a system is presented and the justifications of technological options are brought with the use of simulation and experimental results. Firstly, neutron-transport calculations allow us to propose two in-vessel regions, namely the above-core and under

  14. French essentials for dummies

    CERN Document Server

    Lawless, Laura K

    2011-01-01

    Just the core concepts you need to write and speak French correctly If you have some knowledge of French and want to polish your skills, French Essentials For Dummies focuses on just the core concepts you need to communicate effectively. From conjugating verbs to understanding tenses, this easy-to-follow guide lets you skip the suffering and score high at exam time. French 101 - get the lowdown on the basics, from expressing dates and times to identifying parts of speech Gender matters - see how a noun's gender determines the articles, adjectives, and pronouns y

  15. Preventive measures against vibration of FBR reactor vessel cooling structure

    International Nuclear Information System (INIS)

    Eguchi, Yuzuru; Tanaka, Nobukazu

    1989-01-01

    The present paper describes the fundamental feature of the fluid-elastic vibration of flexible overflow weir, as observed in the French demonstration fast breeder reactor, Super Phenix-1. In the experimental study, the instability criterion of the fluid-elastic vibration was studied by using a simple experimental apparatus of a rectangular tank separated by a flexible weir. A spring-mass model was developed to clarify the mechanism of the instability. The instability condition was analytically derived from the equations of the spring-mass model. The equations of the spring-mass model was also computationally integrated in time to simulate the temporal evolution of the fluid-elastic vibration. The comparison between the experimental and theoretical results indicates that the present theoretical model is capable of predicting most of the physical tendencies observed in the experiment. The present study revealed that the lag time of waterfall at the weir is the most influential parameter among other hydro-elastic parameters. (author)

  16. French in Culinary World

    Directory of Open Access Journals (Sweden)

    Rila Hilma

    2011-10-01

    Full Text Available More than million foods have been made by people from all over the world in the latest years. People now try to create new cooks and make some creativity on it. Then, cooking which the field is culinary has become an art because it needs an artistic value to decorate the food, a good taste and proper technique in processing delicious food in order to make it a masterpiece. French culinary is as famous as the Eiffel tower in the heart of the country, Paris. Most of fine dining international restaurants apply the French menu and cooking. This article presents an overview about the French element in culinary world; starts from its history, kitchen organization, French menu spelling, and French cooking vocabulary. The discussion proceeds library research to compile the data. Later, the art of culinary is interesting to be learned because it contains the classical history of world civilization, in this case French civilization. The issue of cooking trend “nouvelle cuisine” was a masterpiece of one of the greatest chef in his time, Escoffier. French culinary is widely well-known in all over the world because of innovation, creativity, and proud. Those are spirits that we must learn.   

  17. The absent father of Sino-French cinema: Contemporary Taiwanese cinema and 1950s French auteurs

    OpenAIRE

    Bloom, ME

    2014-01-01

    © 2014 Taylor & Francis. In contemporary Sino-French cinema, father characters who are dead, long lost or geographically distant leave gaping holes in the lives of the offspring left behind. The absent fathers in Sino-French films by Taiwanese auteurs Cheng Yu-chieh, Hou Hsiao-hsien and Tsai Ming-liang serve as metaphors for French auteurs. French New Wave films constitute the majority of the intertexts; however, early 1950s French cinema and even late nineteenth-century painting reflect th...

  18. Development of Gender Typicality and Felt Pressure in European French and North African French Adolescents.

    Science.gov (United States)

    Hoffman, Adam J; Dumas, Florence; Loose, Florence; Smeding, Annique; Kurtz-Costes, Beth; Régner, Isabelle

    2017-11-14

    Trajectories of gender identity were examined from Grade 6 (M age  = 11.9 years) to Grade 9 in European French (n = 570) and North African French (n = 534) adolescents, and gender and ethnic group differences were assessed in these trajectories. In Grade 6, boys of both ethnic groups reported higher levels of gender typicality and felt pressure for gender conformity than girls. European French girls and boys and North African French girls reported decreasing gender typicality from Grade 6 to Grade 9, whereas North African French boys did not change. Felt pressure decreased among girls, did not change in European French boys, and increased in North African French boys. Ethnic and gender differences in gender identity development are discussed. © 2017 The Authors. Child Development © 2017 Society for Research in Child Development, Inc.

  19. English and French courses

    CERN Multimedia

    2014-01-01

    If one of your New Year’s resolutions is to learn a language, there is no excuse anymore!   You can attend one of our English or French courses and you can practise the language with a tandem partner! General and Professional French Courses The next session will take place from 27 January to 4 April 2014. These courses are open to all persons working on the CERN site, and to their spouses. Oral Expression This course is aimed at students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. The next session will take place from 27 January to 4 April 2014. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. The next session will take place from 27 January to 4 April 2014. Cours d’anglais général et professionnel La prochaine session se déroulera du 3 mars a...

  20. R and D Trends For The Future Sodium Fast Reactors In France

    International Nuclear Information System (INIS)

    Dufour, Ph.; Anzieu, P.; Lecarpentier, D.; Serpantie, JP.

    2006-01-01

    The sodium fast reactors are the natural Generation IV candidate, thanks to their strong potential for incineration and/or breeding that allow drastic fissile materials economy and fission waste products recycling or transmutation. The question is now to make evolve the existing or past projects of reactors to systems fully compatible with Generation IV objectives, in particular with regard to the economy, durability and safety. This work must be achieved in an international frame which requires a sharing of the objectives and will allow, in the long term, the sharing of the activities. However, in order to ensure the overall coherence of the various development programs defined within the Gen-IV framework, it is necessary to define a new SFR development plan based on the experience gained in France (Phenix, Superphenix) and Europe, in the EFR project. The commonly agreed SFR system issues to be improved or further investigated are its capital cost, safety issues (sodium risks, core criticality accidents), and in-service inspection and maintenance technology. (authors)

  1. Corn content of French fry oil from national chain vs. small business restaurants.

    Science.gov (United States)

    Jahren, A Hope; Schubert, Brian A

    2010-02-02

    Several issues, ranging from sustainability to health, may interest the consumers in the corn content of their food. However, because restaurants are excluded from the Nutrition Labeling and Education Act of 1990, national chain restaurants provide nonspecific ingredient information and small businesses supply none. We measured the carbon isotope composition of fry oil in French fries purchased from 68 (67%) of the 101 national chain fast food restaurants on Oahu (i.e., McDonald's, Burger King, Wendy's, Arby's, and Jack in the Box), and paired this with a similar number of small businesses (n = 66) to calculate minimum percent contribution of corn to total fry oil. We found that the majority (69%) of the national chain restaurants served fries containing corn oil, whereas this was true for only a minority (20%) of the small businesses. Corn oil is more expensive than soybean oil (for example) when purchased from a small business supplier, suggesting that large-scale corporate agreements are necessary to make corn oil frying cost-effective. When considering French fry oil along with corn-fed beef and chicken, as well as high-fructose corn syrup-sweetened soda, we see the pervasive influence of corn as an ingredient in national chain fast food.

  2. French public finances at risk?

    Directory of Open Access Journals (Sweden)

    Creel Jérôme

    2014-01-01

    Full Text Available Using descriptive evidence, this paper contributes to the debate on French public finances’ consolidation by examining the long-term sustainability of France’s fiscal position. We trace the historical trends of government’s tax receipts and expenditures. We illustrate that while the level of public expenditure in France is larger than in the Euro Area, its trend is comparable to its neighbours. French net debt is comparable to Eurozone’s while French net wealth remains positive. However, the French tax system is not progressive with only 6% of compulsory levies raised that way, and too complex. The paper then acknowledges the efficient debt management of French authorities. As a conclusion, we see no risk of future unsustainability linked to the nature or the level of current French public finances.

  3. The French coal board and French society

    International Nuclear Information System (INIS)

    Ladoucette, Ph. de

    2004-01-01

    On 19 April 1946 the French national assembly passed a law for nationalizing the mineral fuel industry by a vote of 516 against only 31. 'Charbonnages de France' (CDF), the French coal board, was created and prospects were promising. During the reconstruction period (1945 - 1960), coal industry was a pillar of the French economy, the production of coal had been steadily growing to reach its top in 1958 with 59 Mt. The sixties showed the beginning of the decline of coal to the benefit of oil, natural gas and later nuclear energy. As early as 1967 CDF had a policy of promoting new industries in regions of mines in order to break down the mono-industry scheme and to favor staff conversion massively. In 1947 the number of people on the payroll of CDF was 360.000, this number was decreasing steadily to reach 23.000 in 1990. In 2004 the last deep mine to work in France was closed down. This article tells the story of coal mining in France by describing its ups and downs and by assessing its social impact

  4. Detector response of the PHENIX Muon Piston Colorimeter for √{Snn} = 200 GeV Au+Au collisons

    Science.gov (United States)

    Kimelman, Benjamin; Phenix Collaboration

    2013-10-01

    Transverse energy is often used to characterize the energy density in ultra-relativistic heavy ion collisions. Most measurements are obtained in the the central rapidity region; however, the PHENIX Muon Piston Calorimeter (MPC), a homogeneous electromagnetic calorimeter, is a useful tool for measuring this quantity in the forward/backward pseudo-rapidity regions. A full Geant3 detector simulation is used for assessing detector response and the effects of particle decays on the measurement of transverse energy in the pseudo-rapidity range 3 . 1 < | η | < 3 . 9 . In 2010, √{SNN} = 200 GeV Au+Au collisons were obtained and are being analyzed. Various event generators are used as input to the detector simulation to help determine the effects of inflow, outflow, and hadronic response of the MPC. We gratefully acknowledge support from NSF grant number 1209240.

  5. French nuclear organization

    International Nuclear Information System (INIS)

    Naudet, G.

    1993-01-01

    The French nuclear organization is characterized by two main features: the small number of firms involved and the role of the Government. In this text we give the French organization for nuclear industry and the role of Government and public authorities. 7 figs

  6. Directory of the French nuclear industry

    International Nuclear Information System (INIS)

    2002-10-01

    This directory includes data sheets on the French companies operating in the nuclear industry. It begins with an introduction containing information on the French nuclear industry: 1 - nuclear power development in France (national energy plan, history, organization, economic advantages, reactors); 2 - French operator: Electricite de France (EdF); 3 - the industry (Areva, Cogema, mining activities, uranium chemistry and enrichment, processing, recycling, engineering, services, Framatome ANP); 4 - R and D and knowledge dissemination: French atomic energy commission (CEA); 5 - nuclear safety, security, control and regulation: nuclear safety authority (ASN), general direction of nuclear safety and radioprotection (DGSNR), institute of radioprotection and nuclear safety (IRSN), radioactive wastes, ANDRA's role; 6 - associations: French atomic forum (FAF), French nuclear industry trade association (GIIN), French nuclear energy society (SFEN), French radiation protection society (SFRP). Then, the data sheets of the directory follows. (J.S.)

  7. French Antilles and Guiana.

    Science.gov (United States)

    1983-11-01

    This discussion of French Antilles and Guiana cover the following: the people, geography, history, government, political conditions, economy, and relations with the US. In 1983 the population totaled 303,000 with an annual growth rate of 0.09%. The infant mortality rate (1981) was 12.6/1000 and life expectancy 68 years. About 98% of the people of Martinique are of Afro European or Afro European Indian descent. The remainder are the old planter families and a sizable number of metropolitan French. Most of the work force are employed in agriculture or food processing and associated industries. Most permanent residents of Guadeloupe are of mixed Afro European descent. A few thousand Metropolitan French reside there. Most French Guianese live along the coast, about 1/2 of them in the capital. Martinique is the northernmost of the Windward Islands, which are part of the Lesser Antilles chain in the Caribbean Sea southeast of Puerto Rico. Guadeloupe comprises 2 of the Leeward Islands, which are also part of the Lesser Antilles chain. French Guiana is located on the northern coast of South America, a few degrees north of the Equator. Indians were the 1st known indigenous inhabitants of French Guiana and the French Antilles. Columbus sighted Guadeloupe in 1493, Martinique in 1493 or 1502, and the Guiana coast probably during his 3rd voyage in 1498. French Guiana, Guadeloupe, and Martinique, as overseas departments of France since 1946, are integral parts of the French Republic. Their relationship to Metropolitan France is somewhat similar to that of Alaska and Hawaii to the counterminous US. Each department has a general council composed of 1 representative elected by each canton. Guadeloupe and Martinique each elect 2 senators to the French Senate and 3 deputies to the National Assembly. French Guiana elects 1 senator and 1 deputy. In each of the 3 departments exist individuals and small political parties that advocate immediate independence, but their adherents form only

  8. 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

  9. General and Professional French Courses

    CERN Multimedia

    HR Department

    2010-01-01

    The next session will take place from 11 October to 17 December 2010. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux, tel. 78144. NEW COURSES Specific French courses -Exam preparation/ We are now offering specific courses in English and French leading to a recognised external examination (e.g. DELF 1 and 2). If you are interested in following one of these courses and have at least an intermediate level of French, please enrol through the following link: French courses or contact: Lucette Fournier, tel.  73483 (French courses).

  10. Radiation heat transfer through the gas of a sodium cooled fast breeder reactor

    International Nuclear Information System (INIS)

    Pradel, P.; Frachet, S.; Petit, D.

    1984-04-01

    Analysis based on results from the COCA test campaign and Germinal mockup of Super Phenix upper shuttings, of the heat transfers and radiation attenuation due to sodium aerosols between the free surface of sodium and the upper shuttings

  11. On the major DYN3D developments for fast reactor design and transient analysis

    International Nuclear Information System (INIS)

    Merk, B.; Kliem, S.

    2013-01-01

    Due to the French project ASTRID, the European CP-ESFR project, and the MYRRHA/FASTEF project, the research work on fast reactors has got a new push in Europe. Additionally to this European projects a strong project is growing in Russia based on the lead cooled fast reactor design BREST. Following this trend, the Institute of Resource Ecology at the Helmholtz-Zentrum Dresden-Rossendorf has decided to start several projects dedicated to fast reactor technology, among them the extension of the well validated LWR core simulator DYN3D. The new developments, first validation results, and the next strategic steps for the adaption of the code for the improved simulation of fast reactor cores are presented. (orig.)

  12. On the major DYN3D developments for fast reactor design and transient analysis

    Energy Technology Data Exchange (ETDEWEB)

    Merk, B.; Kliem, S. [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Reactor Safety Div.

    2013-07-01

    Due to the French project ASTRID, the European CP-ESFR project, and the MYRRHA/FASTEF project, the research work on fast reactors has got a new push in Europe. Additionally to this European projects a strong project is growing in Russia based on the lead cooled fast reactor design BREST. Following this trend, the Institute of Resource Ecology at the Helmholtz-Zentrum Dresden-Rossendorf has decided to start several projects dedicated to fast reactor technology, among them the extension of the well validated LWR core simulator DYN3D. The new developments, first validation results, and the next strategic steps for the adaption of the code for the improved simulation of fast reactor cores are presented. (orig.)

  13. CARRYING OF FRENCH VISAS FOR HOLDERS OF CATEGORY 'EF' FRENCH ATTESTATIONS DE FONCTIONS

    CERN Multimedia

    Service des Relations avec les Pays Hôtes

    1999-01-01

    The French Ministry of Foreign Affairs has informed the Organisation that members of the personnel resident in Switzerland and holding Category 'EF' French Attestations de functions are not obliged to be in possession of French visas. When temporarily travelling through France on OFFICIAL CERN BUSINESS, provided they are carrying the valid Attestation and a valid national passport with them.Relations with the Host States Servicehttp://www.cern.ch/relations/Tel. 72848

  14. Flirting with French

    CERN Document Server

    Alexander, William

    2015-01-01

    William Alexander is not just a Francophile, he wants to be French. It's not enough to explore the country, to enjoy the food and revel in the ambience, he wants to feel French from the inside. Among the things that stand in his way is the fact that he can't actually speak the language. Setting out to conquer the language he loves (but which, amusingly, does not seem to love him back), Alexander devotes himself to learning French, going beyond grammar lessons and memory techniques to delve into the history of the language, the science of linguistics, and the art of translation. Along

  15. French Wines on the Decline?:

    DEFF Research Database (Denmark)

    Steiner, Bodo

    2004-01-01

    French wines, differentiated by geographic origin, served for many decades as a basis for the French success in the British wine market. However in the early 1990s, market share began to decline. This article explores the values that market participants placed on labelling information on French...

  16. 7 CFR 993.7 - French prunes.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false French prunes. 993.7 Section 993.7 Agriculture... Order Regulating Handling Definitions § 993.7 French prunes. French prunes means: (a) Prunes produced from plums of the following varieties of plums: French (Prune d'Agen, Petite Prune d'Agen), Coates (Cox...

  17. Leak before break application in French PWR plants under operation

    Energy Technology Data Exchange (ETDEWEB)

    Faidy, C. [EDF SEPTEN, Villeurbanne (France)

    1997-04-01

    Practical applications of the leak-before break concept are presently limited in French Pressurized Water Reactors (PWR) compared to Fast Breeder Reactors. Neithertheless, different fracture mechanic demonstrations have been done on different primary, auxiliary and secondary PWR piping systems based on similar requirements that the American NUREG 1061 specifications. The consequences of the success in different demonstrations are still in discussion to be included in the global safety assessment of the plants, such as the consequences on in-service inspections, leak detection systems, support optimization,.... A large research and development program, realized in different co-operative agreements, completes the general approach.

  18. Corn content of French fry oil from national chain vs. small business restaurants

    OpenAIRE

    Jahren, A. Hope; Schubert, Brian A.

    2010-01-01

    Several issues, ranging from sustainability to health, may interest the consumers in the corn content of their food. However, because restaurants are excluded from the Nutrition Labeling and Education Act of 1990, national chain restaurants provide nonspecific ingredient information and small businesses supply none. We measured the carbon isotope composition of fry oil in French fries purchased from 68 (67%) of the 101 national chain fast food restaurants on Oahu (i.e., McDonald’s, Burger Kin...

  19. 21 CFR 169.115 - French dressing.

    Science.gov (United States)

    2010-04-01

    ... 21 Food and Drugs 2 2010-04-01 2010-04-01 false French dressing. 169.115 Section 169.115 Food and... § 169.115 French dressing. (a) Description. French dressing is the separable liquid food or the..., lecithin, or polyglycerol esters of fatty acids. (d) Nomenclature. The name of the food is “French dressing...

  20. Optimum use of CDOT French and Hamburg data (French and Hamburg tests).

    Science.gov (United States)

    2013-11-01

    The Colorado Department of Transportation (CDOT) has been collecting data from the Hamburg Rutter and the : French Rutter for over 20 years. No specifications have been written in that time for either the Hamburg Rutter : or the French Rutter. This r...

  1. English Grammar for Students of French.

    Science.gov (United States)

    Morton, Jacqueline

    This grammar is a self-study manual intended to aid native speakers of English who are beginning the study of French. It is designed to supplement the French textbook, not to replace it. The common grammatical terms that are necessary for learning to speak and write French are explained in English and illustrated by examples in both French and…

  2. French visas

    CERN Multimedia

    2007-01-01

    The French Ministry of Foreign Affairs (hereinafter "MAE") has informed CERN of the following new regulations governing the visas required when submitting requests for French legitimation documents (cf. in particular paragraph b) below concerning the facilities recently granted to certain categories of persons who are not nationals of Switzerland or of a member state of the European Economic Area). This notification replaces that which appeared in Bulletin No.19/2006 (ref. CERN/DSU-DO/RH/13173/Rev.). 1. Special residence permit ("Titre de séjour special") To qualify for a special residence permit from the MAE, persons who are not nationals of Switzerland or of a member state of the European Economic Area (hereinafter "EEA") must present the following upon arrival at CERN: a)\teither a “D”-type (long-stay) French visa marked “carte PROMAE à solliciter à l’arrivée”, even if they are not subject to the requirement to obtain an entrance and short-stay visa in France...

  3. Fast reactors bulk sodium coolant disposal NOAH process application

    International Nuclear Information System (INIS)

    Magny, E. de; Berte, M.

    1997-01-01

    Within the frame of the fast reactors decommissioning, the becoming of contaminated sodium coolant from primary, secondary and auxiliary circuits is an important aspect. The 'NOAH' sodium disposal process, developed by the French Atomic Energy Commission (CEA), is presented as the only process, for destroying large quantities of contaminated sodium, that has attained industrial status. The principles and technical options of the process are described and main advantages such as safety , operating simplicity and compactness of the plant are put forward. The process has been industrially validated in 1993/1994 by successfully reacting the 37 metric tons of primary contaminated sodium from the French Rapsodie experimental reactor. The main outstanding aspects and experience gained from this so called 'DESORA' operation (DEstruction of SOdium from RApsodie) are recalled. Another industrial application concerns the current project for destroying more than 1500 metric tons of contaminated sodium from the British PFR (Prototype Fast Reactor) in Scotland. Although the design is in the continuity of DESORA, it has taken into account the specific requirements of PFR application and the experience feed back from Rapsodie. The main technical options and performances of the PFR sodium reaction unit are presented while mentioning the design evolution. (author)

  4. European-French Cross-Cultural Adaptation of the Developmental Coordination Disorder Questionnaire and Pretest in French-Speaking Switzerland.

    Science.gov (United States)

    Ray-Kaeser, Sylvie; Satink, Ton; Andresen, Mette; Martini, Rose; Thommen, Evelyne; Bertrand, Anne Martine

    2015-05-01

    The Developmental Coordination Disorder Questionnaire (DCDQ'07) is a Canadian-English instrument recommended for screening children aged 5 to 15 years who are at risk for developmental coordination disorder. While a Canadian-French version of the DCDQ'07 presently exists, a European-French version does not. To produce a cross-cultural adaptation of the DCDQ'07 for use in areas of Europe where French is spoken and to test its cultural relevance in French-speaking Switzerland. Cross-cultural adaptation was done using established guidelines. Cultural relevance was analyzed with cognitive interviews of thirteen parents of children aged 5.0 to 14.6 years (mean age: 8.5 years, SD = 3.4), using think-aloud and probing techniques. Cultural and linguistic differences were noted between the European-French, the Canadian-French, and the original versions of the DCDQ'07. Despite correct translation and expert committee review, cognitive interviews revealed that certain items of the European-French version were unclear or misinterpreted and further modifications were needed. After rewording items as a result of the outcomes of the cognitive interview, the European-French version of the DCDQ'07 is culturally appropriate for use in French-speaking Switzerland. Further studies are necessary to determine its psychometric properties.

  5. Stainless steel corrosion in French LMFBR - Feedback and prevention against risks

    International Nuclear Information System (INIS)

    Grabon, V.; Brissonneau, L.; Billey, C.

    2015-01-01

    This paper deals with the mechanisms and the conditions leading to the most threatening corrosion risks specific to the use of sodium at high temperature as coolant in FBR (Fast Breeder Reactors) - apart from wastage (rapid erosion-corrosion of the steam generator tubes by sodium hydroxide due to steam-water leaks in sodium): Stress Corrosion Cracking (SCC) induced in sodium polluted by sodium hydroxide (following sodium-water reaction or incomplete cleaning of component), SCC induced by caustic solution during maintenance operations (cleaning of component or repair on drained sodium circuit inducing moist air ingress), and Intergranular Attack (IGA) induced on sensitized stainless steels by acid solutions used during maintenance operations (decontamination of component, chemical cleaning). These risks are illustrated by some examples of corrosion encountered through Phenix experience or in CEA sodium loops. The paper also describes the solutions and the preventive measures that have been put in place against these corrosion risks, in the form of design rules and operating procedures. Generally the plant operator cannot control the material parameters (metal composition, aging, stress) during the lifetime of the facility. Thus most of the time preventive measures consist in excluding at least one of the two other factors related to the chemical environment and/or to the operating conditions. Moreover corrosion of the primary components during cleaning and decontamination operations before repairing should be carefully examined to authorize their reuse in the reactor

  6. Study of the open charm and Drell-Yan production in p + p collisions at 200 GeV with the Phenix detector at RHIC; Etude de la production de charme ouvert et de Drell-Yan dans les collisions p + p a 200 GeV avec le detecteur Phenix a RHIC

    Energy Technology Data Exchange (ETDEWEB)

    Gadrat, S

    2005-09-15

    Ultra-relativistic heavy ions collisions allow the study of nuclear matter under extreme conditions of temperature and pressure and, more specifically, of a new phase of nuclear matter: the quarks and gluons plasma (QGP). The RHIC collider, located at the Brookhaven National Laboratory (Usa), produces such collisions. PHENIX, one of the four operational detectors at the collider, is the only one capable of measuring muons. In this dissertation, we present a dimuon data analysis, which data have been collected by PHENIX in p + p collisions during two data taking runs (3 and 4). p + p collisions provide a requisite reference for the understanding of heavy ions collisions. The aim of the analysis discussed in this dissertation is to extract the cross sections of the main physical components of the dimuon spectrum observed at RHIC for p + p collisions: J/{psi}, open charm and Drell-Yan. This analysis is based on a global line shape fit of the dimuon mass spectrum. This fit has been possible thanks to prior simulation study of the mass distribution shapes of these different components. Production yields were obtained from the fit. Lastly, the response function study for each components and the use of various efficiencies led to the estimate of the different production cross sections. The results have been compared to other existing measurements and show an overall good agreement. The work presented in this dissertation offers a first estimate of the open charm production cross section in the dimuon channel, as well as a first estimate of the Drell-Yan production cross section at RHIC for p + p collisions: {sigma}(J/{psi} {yields} {mu}{mu}) = (2.9 {+-} 0.1) {mu}b; {sigma}(cc-bar {yields} {mu}{mu}) = (0.96 {+-} 0.18) mb; {sigma}(Drell-Yan {yields} {mu}{mu}) = (0.20 {+-} 0.04) {mu}b.

  7. Access French

    CERN Document Server

    Grosz, Bernard

    2014-01-01

    Access is the major new language series designed with the needs of today's generation of students firmly in mind. Whether learning for leisure or business purposes or working towards a curriculum qualification, Access French is specially designed for adults of all ages and gives students a thorough grounding in all the skills required to understand, speak, read and write contemporary French from scratch. The coursebook consists of 10 units covering different topic areas, each of which includes Language Focus panels explaining the structures covered and a comprehensive glossary. Learning tips

  8. The relationship of French people with energy

    International Nuclear Information System (INIS)

    Levy, Jean-Daniel; Potereau, Julien; Gautier, Antoine

    2017-12-01

    This Power Point document presents graphs and tables containing results of a survey performed on the relationship French people have with energy. After a presentation of the survey methodology, it addresses how France commitment in the struggle against climate change is perceived (French people think that their country could do better), which perceptions French people have of stakes and of the French energy policy (the management of the energy issue is perceived as perfectible, and French people have a positive view on energy transition and on the development of renewable energies), and which investments French people stand for (French people are in favour of a more important role of Europe and of citizen cooperatives in the field of energy)

  9. Development of the French Photovoltaic Program

    Energy Technology Data Exchange (ETDEWEB)

    Brunet, M.

    1980-07-01

    The French photovoltaic research program is reviewed, listing companies involved. Projections of module and system costs are discussed. French industrial experience in photovoltaics is reviewed and several French systems operating in developing countries are mentioned. (MHR)

  10. Fuel cycle: the transition between the third and the fourth generation of reactors; Cycle du combustible: faire la transition vers les 3eme et 4eme generations de reacteurs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    Many challenges arrive today for the french research and development on the fuel cycle: promote the industrial technologies, improve the world increase of the nuclear and adapt the fuel cycle technologies to the future reactors. In this framework the report presents after a recall on the fuel cycle, the researches on the fuel, the optimization of the recycling, the wastes management, the simulation and Phenix an experimentation tool for the fuel. (A.L.B.)

  11. Fuel cycle: the transition between the third and the fourth generation of reactors

    International Nuclear Information System (INIS)

    2008-01-01

    Many challenges arrive today for the french research and development on the fuel cycle: promote the industrial technologies, improve the world increase of the nuclear and adapt the fuel cycle technologies to the future reactors. In this framework the report presents after a recall on the fuel cycle, the researches on the fuel, the optimization of the recycling, the wastes management, the simulation and Phenix an experimentation tool for the fuel. (A.L.B.)

  12. Fast foods perception among adolescents by gender and weight status.

    Science.gov (United States)

    Allehdan, Sabika S; Tayyem, Reema F; Bawadi, Hiba A; Al-Awwad, Narmeen J; Al-Mannai, Mariam; Musaiger, Abdulrahman O

    2017-03-01

    Fast food restaurants have become widespread in both developed and developing countries due to nutritional and economic transitions. The frequency of fast food intake is relatively high among adolescents; however, fast food consumption is positively associated with total energy intake and obesity in adolescents. This study aimed to examine the perception of Jordanian adolescents towards fast foods relative to gender and obesity. A cross-sectional survey was conducted on 400 boys and 395 girls, aged 15-18 years. The adolescents completed a validated questionnaire to measure the perception of adolescents towards fast foods during the year 2013-2014. Weight and height were measured. Numbers who were non-overweight, overweight, and obese were calculated for each age and sex using the International Obesity Task Force (IOTF) standard. The majority of participants perceived foods which are eaten as sandwiches as fast foods. A significant difference between boy and girl adolescents was reported regarding perception of French fries ( p fast foods. Girls were significantly more enthusiastic than boys to consider cuscusi plate ( p foods ( p foods ( p foods ( p foods ( p fast foods. The difference between obese and non-obese regarding the perception of fast foods was only significant among boy participants. Western or non-Arab foods, food prepared fast and eaten fast in self-service outlets, and food rich in calories were significantly perceived as fast food by Jordanian adolescents ( p foods as fast foods or non-fast foods was significantly different between both genders as well as in obese and non-obese male Jordanian adolescents.

  13. Pre-Pregnancy Fast Food Consumption Is Associated with Gestational Diabetes Mellitus among Tehranian Women.

    Science.gov (United States)

    Lamyian, Minoor; Hosseinpour-Niazi, Somayeh; Mirmiran, Parvin; Moghaddam Banaem, Lida; Goshtasebi, Azita; Azizi, Fereidoun

    2017-03-01

    The aim of this study was to evaluate the association between fast food consumption and gestational diabetes mellitus (GDM) among Tehranian women. This study was conducted over a 17-month period, on a random sample of pregnant women ( n = 1026), aged 18-45 years, attending prenatal clinics in five hospitals affiliated with universities of medical sciences, located in different districts of Tehran, Iran. Dietary data were collected during gestational age ≤6 weeks, using a 168-item valid and reliable food frequency questionnaire. Consumption of total fast foods including hamburgers, sausages, bologna (beef), pizza and French fries was calculated. Between 24 and 28 weeks of gestation, all pregnant women underwent a scheduled 100 g 3 h oral glucose tolerance test. GDM was defined according to the American Diabetes Association definition. The mean age and pre-pregnancy body mass index BMI of participants were 26.7 ± 4.3 years and 25.4 ± 4.5 Kg/m², respectively. A total of 71 women developed GDM. After adjustment for confounders, the OR (95% CI) for GDM for total fast food consumption was 2.12 (1.12-5.43) and for French fries it was 2.18 (1.05-4.70). No significant association was found between hamburgers, sausages, bologna (beef), pizza and GDM. Fast food consumption in women of reproductive age was found to have undesirable effects in the prevalence of GDM.

  14. The effect of food type (fish nuggets or French fries) on oil blend degradation during repeated frying.

    Science.gov (United States)

    Flores-Álvarez, María Del Carmen; Molina-Hernández, Erika F; Hernández-Raya, José Concepción; Sosa-Morales, María Elena

    2012-11-01

    Oil that is reused multiple times for deep frying goes through changes in chemical composition and physical characteristics, affecting the quality of the fried foods. In this study, the effect of the food type (fish nuggets or French fries) on the degradation of an oil blend during the deep-fat frying of each food at 180°C during 12 days was determined, and the characteristics of the fried products were evaluated. The degradation of oil during repeated use was relatively faster when fish nuggets were fried than when French fries were fried, as higher values of total polar compounds were obtained. The results are useful for producers of French fries and fish nuggets, such as restaurants or fast foods sellers, providing them with practical guidelines within the permitted values established by the regulatory authorities. The studied foods have high economic importance and are different in their composition. Under the studied conditions, the tested oil blend may be used during 4 d (4 h per day) with a daily replenishment, without discarding the oil when frying fish nuggets, and must be discarded after 8 d when French fries are processed. This suggestion allows preparing safe fried foods for consumers. © 2012 Institute of Food Technologists®

  15. Teaching for Content: Greek Mythology in French.

    Science.gov (United States)

    Giauque, Gerald S.

    An intermediate-level university French course in Greek mythology was developed to (1) improve student skills in reading, writing, speaking, and comprehending French, (2) familiarize students with Greek mythology, and (3) prepare students to deal better with allusions to Greek mythology in French literature. The texts used are a French translation…

  16. French experience and prospects in the reprocessing of fast breeder reactor fuels

    International Nuclear Information System (INIS)

    Megy, J.

    1983-06-01

    Experience acquired in France in the field of reprocessing spent fuels from fast breeder reactors is recalled. Emphasis is put on characteristics and quantities of spent fuels reprocessed in La Hague and Marcoule facilities. Then reprocessing developments with the realisation of the new pilot plant TOR at Marcoule, new equipments and study of industrial reprocessing units are reviewed [fr

  17. The decommissioning of nuclear power stations. France and the American experience

    International Nuclear Information System (INIS)

    Tonnac, Alain de; Perves, Jean-Pierre

    2013-01-01

    After having noticed that many electronuclear reactors have already been stopped, and that some research reactors have just been dismantled in Grenoble by the CEA, and evoked the main involved actors (ASN, IRSN, ANDRA), some characteristics of the French situation are outlined: the strategy adopted by EDF for a fast dismantling process, the long legal delays for stopping, dismantling and downgrading of sites, the absence of waste radioactivity release thresholds, and the responsibility of operators for dismantling operations. The main steps of a station dismantling are indicated and discussed: end of exploitation; steps of deconstruction (evacuation of big components, elimination of building radioactivity, building destruction, site partial or total reconversion). The French authorization process is briefly commented. Then, the American experience and situation is commented in terms of number of concerned sites, of site situation, but also in terms of organisation and selected technologies. Critical steps are outlined as well as improvements obtained in terms of exposure, of waste volumes, of effluent filtration capacities, and of cutting methods. The next part proposes an overview of the situation or steps of decommissioning in France for different sites: the Chooz PWR, the fleet of first generation reactors, graphite gas reactors, the Brennilis power station and Super Phenix in Creys Malville. Costs and delays are briefly evoked for the USA as well as for France

  18. Anglicism in the French language

    Directory of Open Access Journals (Sweden)

    Firoozeh Asghari

    2014-09-01

    Full Text Available There is no question nowadays as to the international and powerful status of English at a global scale and, consequently, as to its presence in non-English speaking countries at different levels.  It is the languages which have mostly influenced French after the Two World War. So that now Anglicism exists in all levels of French. In this paper, besides the phenomenon of Anglicism, we will mainly focus on the reasons of increasing French interest in using of this phenomenon and also on the reactions taken against it in France. The method used in this research is descriptive – analytical.   The Result of this study shows that there is no purely linguistic reason for “Anglicism” in a country like France. In fact this paper remarks that the strong impact of English on French rather than being influenced by linguistic reasons is influenced by the cultural & social reasons. Additionally, the finding shows that the French especially the youth like using English for several reasons which include “prestige”, “snobbery” and “superiority”. Amongst the mentioned reasons in this paper, what caused the French to worry about the spread of Anglicism is due to fear of the American cultural influence, what is changing in the American cultural hegemony.

  19. French nuclear experience

    International Nuclear Information System (INIS)

    Reynolds, M.; Barre, B.

    1984-01-01

    The French nuclear attache at the French Embassy in Washington discusses his country's energy program and his role at the embassy as a representative of the French nuclear industry. He reviews the nuclear program's growth since it began in 1945, and the impetus of the OPEC oil embargo to accelerate the program since 1973. The success of France's nuclear program is due to a convergence of reasons that include incentive, the existence of a single utility that could design and manage a project of this magnitude, and the decision to focus on the pressurized water reactor (PWR) built by a single supplier and offering the benefits of standardization. Controlling the fuel cycle is the basic philosophy of both the PWR and the breeder program. Barre recommends policies of pre-approved sites, standardization, and licensing reform for the US

  20. Fuel pin behavior under slow ramp-type transient-overpower conditions in the CABRI-FAST experiments

    International Nuclear Information System (INIS)

    Fukano, Yoshitaka; Onoda, Yuichi; Sato, Ikken; Charpenel, Jean

    2009-01-01

    In the CABRI-FAST experimental program, four in-pile tests were performed with slow power-ramp-type transient-overpower conditions (called hereafter as 'slow TOP') to study transient fuel pin behavior under inadvertent control rod withdrawal events in liquid metal cooled fast breeder reactors. Annular-pellet fuel pins were used in three tests, while a solid-pellet fuel pin was used in the other test. All of these pins were pre-irradiated in Phenix. The slow TOP test with a solid-pellet fuel pin was realized as a comparatory test against an existing test (E12) in the CABRI-2 program. In the CABRI-FAST test (BCF1), a power ramp rate of 3% Po/s was applied, while in the CABRI-2 test, 1% Po/s was adopted. Moreover, overpower condition was maintained for a few seconds beyond the observed pin failure in the BCF1 test. In spite of the different power ramp rates, evaluated fuel thermal conditions at the observed failure time are quite similar. The continued overpower condition in the BCF1 test resulted in gradual degradation of the pin structure providing information effective for evaluation of various accident scenarios. Three slow TOP tests with the annular fuel in the CABRI-FAST program resulted in no pin failure showing high failure threshold. Based on post-test examination data and a theoretical evaluation, it was concluded that intra-pin free spaces, such as central hole, macroscopic cracks and fuel-cladding gap effectively mitigated fuel cladding mechanical interaction. It was also clarified that cavity pressurization became effective only in case of very large amount of fuel melting. Furthermore, such cavity pressurization was effectively mitigated by a molten-fuel squirting into the upper blanket region pushing the blanket pellets upward. These CABRI FAST slow TOP tests, in combination with the existing CABRI and TREAT tests, provided an extended slow TOP test database with various fuel and transient conditions. (author)

  1. Routledge French technical dictionary

    CERN Document Server

    1994-01-01

    The French-English volume of this highly acclaimed set consists of some 100,000 keywords in both French and English, drawn from the whole range of modern applied science and technical terminology. Covers over 70 subject areas, from engineering and chemistry to packaging, transportation, data processing and much more.

  2. Data oriented job submission scheme for the PHENIX user analysis in CCJ

    International Nuclear Information System (INIS)

    Nakamura, T; En'yo, H; Ichihara, T; Watanabe, Y; Yokkaichi, S

    2011-01-01

    The RIKEN Computing Center in Japan (CCJ) has been developed to make it possible analyzing huge amount of data corrected by the PHENIX experiment at RHIC. The corrected raw data or reconstructed data are transferred via SINET3 with 10 Gbps bandwidth from Brookheaven National Laboratory (BNL) by using GridFTP. The transferred data are once stored in the hierarchical storage management system (HPSS) prior to the user analysis. Since the size of data grows steadily year by year, concentrations of the access request to data servers become one of the serious bottlenecks. To eliminate this I/O bound problem, 18 calculating nodes with total 180 TB local disks were introduced to store the data a priori. We added some setup in a batch job scheduler (LSF) so that user can specify the requiring data already distributed to the local disks. The locations of data are automatically obtained from a database, and jobs are dispatched to the appropriate node which has the required data. To avoid the multiple access to a local disk from several jobs in a node, techniques of lock file and access control list are employed. As a result, each job can handle a local disk exclusively. Indeed, the total throughput was improved drastically as compared to the preexisting nodes in CCJ, and users can analyze about 150 TB data within 9 hours. We report this successful job submission scheme and the feature of the PC cluster.

  3. Data oriented job submission scheme for the PHENIX user analysis in CCJ

    Science.gov (United States)

    Nakamura, T.; En'yo, H.; Ichihara, T.; Watanabe, Y.; Yokkaichi, S.

    2011-12-01

    The RIKEN Computing Center in Japan (CCJ) has been developed to make it possible analyzing huge amount of data corrected by the PHENIX experiment at RHIC. The corrected raw data or reconstructed data are transferred via SINET3 with 10 Gbps bandwidth from Brookheaven National Laboratory (BNL) by using GridFTP. The transferred data are once stored in the hierarchical storage management system (HPSS) prior to the user analysis. Since the size of data grows steadily year by year, concentrations of the access request to data servers become one of the serious bottlenecks. To eliminate this I/O bound problem, 18 calculating nodes with total 180 TB local disks were introduced to store the data a priori. We added some setup in a batch job scheduler (LSF) so that user can specify the requiring data already distributed to the local disks. The locations of data are automatically obtained from a database, and jobs are dispatched to the appropriate node which has the required data. To avoid the multiple access to a local disk from several jobs in a node, techniques of lock file and access control list are employed. As a result, each job can handle a local disk exclusively. Indeed, the total throughput was improved drastically as compared to the preexisting nodes in CCJ, and users can analyze about 150 TB data within 9 hours. We report this successful job submission scheme and the feature of the PC cluster.

  4. The common P446L polymorphism in GCKR inversely modulates fasting glucose and triglyceride levels and reduces type 2 diabetes risk in the DESIR prospective general French population.

    Science.gov (United States)

    Vaxillaire, Martine; Cavalcanti-Proença, Christine; Dechaume, Aurélie; Tichet, Jean; Marre, Michel; Balkau, Beverley; Froguel, Philippe

    2008-08-01

    Hepatic glucokinase (GCK) is a key regulator of glucose storage and disposal in the liver, where its activity is competitively modulated, with respect to glucose, by binding to glucokinase regulatory protein (GCKR) in the presence of fructose 6-phosphate. Genome-wide association studies for type 2 diabetes identified GCKR as a potential locus for modulating triglyceride levels. We evaluated, in a general French population, the contribution of the GCKR rs1260326-P446L polymorphism to quantitative metabolic parameters and to dyslipidemia and hyperglycemia risk. Genotype effects of rs1260326 were studied in 4,833 participants from the prospective DESIR (Data from an Epidemiological Study on the Insulin Resistance syndrome) cohort both at inclusion and using the measurements at follow-up. The minor T-allele of rs1260326 was strongly associated with lower fasting glucose (-1.43% per T-allele; P = 8 x 10(-13)) and fasting insulin levels (-4.23%; P = 3 x 10(-7)), lower homeostasis model assessment of insulin resistance index (-5.69%; P = 1 x 10(-8)), and, conversely, higher triglyceride levels (3.41%; P = 1 x 10(-4)) during the 9-year study. These effects relate to a lower risk of hyperglycemia (odds ratio [OR] 0.79 [95% CI 0.70-0.88]; P = 4 x 10(-5)) and of incident cases during the study (hazard ratio [HR] 0.83 [0.74-0.95]; P = 0.005). Moreover, an additive effect of GCKR rs1260326(T) and GCK (-30G) alleles conferred lower fasting glycemia (P = 1 x 10(-13)), insulinemia (P = 5 x 10(-6)), and hyperglycemia risk (P = 1 x 10(-6)). GCKR-L446 carriers are protected against type 2 diabetes despite higher triglyceride levels and risk of dyslipidemia, which suggests a potential molecular mechanism by which these two components of the metabolic syndrome can be dissociated.

  5. Behavior of a bundle of fast fuel pins under irradiation

    International Nuclear Information System (INIS)

    Marbach, G.; Millet, P.; Robert, J.; Languille, A.

    1979-01-01

    In the French design of fuel elements for fast reactors, great deformation of pins can bring about interaction with the hexagonal tube through the spacer wires. The change in such bundles is described here when the diameter of the cladding increases and the outcome of this reaction (bending and ovalization of pins) is calculated with a simplified model. It is shown that the results achieved agree well with the experimental observations [fr

  6. French PWR safety philosophy

    International Nuclear Information System (INIS)

    Conte, M.

    1986-05-01

    Increasing knowledge and lessons learned from starting and operating experience of French nuclear power plants, completed by the experience learned from the operation of foreign reactors, has contributed to the improvement of French PWR design and safety philosophy. Based on a deterministic approach, the French safety analysis was progressively completed by a probabilistic approach, each of them having possibilities and limits. As a consequence of the global risk objective set in 1977 for nuclear reactors, safety analysis was extended to the evaluation of events more complex than the conventional ones, and later to the evaluation of the feasibility of the offsite emergency plans in case of severe accidents

  7. The French and energy

    International Nuclear Information System (INIS)

    Rouquette, Celine; Moreau, Sylvain; Bottin, Anne; Reperant, Patricia

    2012-08-01

    In 2012, as in 2011, the French are favourable to renewable energy. If they could, around 60% of them would opt for solar, fuelwood or heat pumps for heating. Wind power is also viewed favourably. Aware of environmental issues, the French are prepared to change their habits in the face of climate change, and two-thirds are even prepared to make sacrifices. One-third declares having already taken action or intending to do so to reduce their energy consumption. The cost of energy remains a central issue: faced with higher prices, half of French people would reduce their consumption. However, information on the subject of energy needs to be improved. (authors)

  8. Health Information in French (français)

    Science.gov (United States)

    ... Biopsy - français (French) Bilingual PDF Health Information Translations Breast Biopsy - français (French) Bilingual PDF Health Information Translations Colposcopy - français (French) Bilingual PDF ...

  9. Study of the production of J/{psi} in Au-Au collisions at 200 GeV per nucleon pair in the PHENIX experiment; Etude de la production du J/{psi} dans les collisions or-or a 200 GeV par paire de nucleons dans l'experience PHENIX

    Energy Technology Data Exchange (ETDEWEB)

    Tram, V.N

    2006-01-15

    One of the most promising signature of Quark Gluon Plasma formation is the heavy quarkonium suppression due to color screening effect. First experiments at the SPS (CERN) have measured an 'anomalous suppression' of the J/{psi} yields (cc-bar state) in central Pb+Pb collisions. However, measurements at different collision energies and with different ions are mandatory to conclude about the discovery of a new state of nuclear matter. This thesis describes the J/{psi} production measured in the dimuon decay channel by the PHENIX experiment (RHIC) studying Au+Au collisions at 200 GeV in the center of mass. The J/{psi} yield measured in the most central collisions is suppressed by a factor of 3 as compared to the yield expected assuming binary scaling. Within the error bars, the suppression does not affect the J/{psi}'s rapidity distribution. However, a broadening of the transverse momentum distribution is observed as compared to the distribution measured in p+p collisions. In order to understand this suppression, 'cold nuclear effects', namely nuclear absorption and shadowing, are to be taken into account. These effects can describe neither the suppression amplitude nor the suppression pattern, suggesting that other mechanisms are involved. Predictions from different models which reproduce the suppression observed by NA50, can hardly describe the PHENIX measurements and over-estimate the suppression at RHIC. Comparisons with predictions from models including recombination of charm quarks give a reasonable description of the suppression amplitude as a function of centrality. However, these predictions are not in good agreement with the observed rapidity and transverse momentum distributions. Finally, one possible scenario is that the temperature at RHIC is not high enough to reach direct J/{psi} melting and that the measured suppression is due to the sequential disappearance from higher mass resonances ({chi}{sub c} and {psi}'). In this

  10. UP1 decommissioning project: initial review of lessons learned

    International Nuclear Information System (INIS)

    Fontana, Ph.; Fraize, G.; Seurat, Ph.

    2008-01-01

    The very first French electricity-generating nuclear reactors (3 gas-graphite reactors operated between 1956 and 1984) and spent fuel reprocessing plant (UP1 and ancillary facilities operated from 1958 to 1997) were located at Marcoule, in southern France. These historic facilities, together with the research labs that contributed to the development and commissioning of the processes implemented, are being decontaminated and dismantled. Other facilities near these nuclear plants will also be shut down in the next few years: the Phenix fast breeder reactor, the Celestin reactors and other ancillary units. Because the UP1 reprocessing plant and its related facilities were used for both commercial and defense activities, a dedicated group comprising three state-owned or private companies (CEA, EdF and COGEMA) was set up as the contracting authority from 1996 to 2004. Today the CEA is the contracting authority at Marcoule and has replaced AREVA NC as the site nuclear operator. AREVA acts as prime contractor for both operation of the main facilities and engineering of the dismantling projects. (authors)

  11. UP1 decommissioning project: initial review of lessons learned

    Energy Technology Data Exchange (ETDEWEB)

    Fontana, Ph.; Fraize, G. [CEA Valrho, Dir. de l' Energie Nucleaire (DEN/DPAD), 30 - Marcoule (France); Seurat, Ph. [AREVA NC, 75 - Paris (France)

    2008-07-01

    The very first French electricity-generating nuclear reactors (3 gas-graphite reactors operated between 1956 and 1984) and spent fuel reprocessing plant (UP1 and ancillary facilities operated from 1958 to 1997) were located at Marcoule, in southern France. These historic facilities, together with the research labs that contributed to the development and commissioning of the processes implemented, are being decontaminated and dismantled. Other facilities near these nuclear plants will also be shut down in the next few years: the Phenix fast breeder reactor, the Celestin reactors and other ancillary units. Because the UP1 reprocessing plant and its related facilities were used for both commercial and defense activities, a dedicated group comprising three state-owned or private companies (CEA, EdF and COGEMA) was set up as the contracting authority from 1996 to 2004. Today the CEA is the contracting authority at Marcoule and has replaced AREVA NC as the site nuclear operator. AREVA acts as prime contractor for both operation of the main facilities and engineering of the dismantling projects. (authors)

  12. French lessons in nuclear power

    International Nuclear Information System (INIS)

    Valenti, M.

    1991-01-01

    In stark contrast to the American atomic power experience is that of the French. Even the disaster at Chernobyl in 1986, which chilled nuclear programs throughout Western Europe, did not slow the pace of the nuclear program of the state-owned Electricite de France (EDF), based in Paris. Another five units are under construction and are scheduled to be connected to the French national power grid before the end of 1993. In 1989, the EDF's 58 nuclear reactors supplied 73 percent of French electrical needs, a higher percentage than any other country. In the United States, for example, only about 18 percent of electrical power is derived from the atom. Underpinning the success of nuclear energy in France is its use of standardized plant design and technology. This has been an imperative for the French nuclear power industry since 1974, when an intensive program of nuclear power plant construction began. It was then, in the aftermath of the first oil embargo, that the French government decided to reduce its dependence on imported oil by substituting atomic power sources for hydrocarbons. Other pillars supporting French nuclear success include retrofitting older plants with technological or design advances, intensive training of personnel, using robotic and computer aids to reduce downtime, controlling the entire nuclear fuel cycle, and maintaining a comprehensive public information effort about the nuclear program

  13. [The medical French-speaking world].

    Science.gov (United States)

    Gouazé, André

    2002-01-01

    Medicine has always been and remains the most solid base of the French-speaking world which was born in Africa and Indochina with the admirable action of "colonial" military physicians, the implantation of the Pasteur Institutes and the emergence of resulting overseas medical schools. Obviously, we are referring to the French-speaking medical world. Since the first International Conference of the Deans of French-Speaking Medical Schools in Abidjan in 1981, today medical schools from 40 French-speaking countries participate. The conference undertakes co-operative medical school initiatives in a multi-lateral spirit, comprised by concrete, practical actions to assist universities in developing countries strive for excellence. These actions, which are conducted with the help of both institutional (AUF, MAE, WHO, UNESCO) and private partners mainly concentrate on promoting medical education of medicine, the evaluation of medical schools, the development of scientific and technical information and training teachers in the methodology of scientific clinical research and in public health. For the future, the Conference has three important objectives, to assist in training researchers and consequently in the development of research centres in emerging countries, to promote continuing medical education in rural areas far from medical schools by taking advantage of modern computer technology, and finally to open horizons toward other communities which speak other languages, and first of all, towards non French-speaking countries who live in a French-speaking environment.

  14. “I Felt Like My Life Had Been Given to Me to Start Over”: Alice Kaplan’s Language Memoir, French Lessons

    Directory of Open Access Journals (Sweden)

    Eleonora Rao

    2016-06-01

    Full Text Available Alice Kaplan’s memoir French Lessons (1993 is a story that deals as much with the issue of language learning as with that of cultural belonging(s. This “language memoir,” as it is typical of this sub-genre, is an intimate tale of the transition between languages and cultures. French Lessons recounts her evolving relationship with French language and culture in various phases of her life: starting from childhood, continuing through her graduate student years at Yale and finally as professor of French at Duke. Soon, however, in this unconventional Bildung, the second language turns out to be a verbal safe-house, an instant refuge when her first language and culture happen to be too uncomfortable. Ultimately, French provides a psychic space and a hiding place. Ultimately, however, as Derrida has shown, we are alienated from both the first and the second; we find ourselves to be more comfortable in one than in the other. This essay will analyze such processes with special attention to the part played by the body in Kaplan’s building as a student and eventually as a teacher. The analysis will be linked with the text’s peculiar narrative style: fast-paced, with simple, concise sentences, nevertheless extremely effective and moving.

  15. What French for Gabonese French Lexicography

    African Journals Online (AJOL)

    user

    administration, international relations, teaching, the media, trade, transport, tourism, .... The present study refutes such as reductive definition of what Gabonese .... language than French limits itself to public speeches and support to linguistics ...... sité Omar Bongo du Gabon: Série Lettres, Droit, Sciences et Médecine: 55-63.

  16. General and professionnal French courses

    CERN Document Server

    2013-01-01

    The next session will take place from 27 January to 4 April 2014. These courses are open to everyone working on the CERN site and to their spouses.   Oral Expression This course is aimed at students with a good knowledge of French who want to enhance their oral communication skills. Activities will include discussions, meeting simulations, role-plays, etc. The next session will take place from 27 January to 4 April 2014. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. The next session will take place from 27 January to 4 April 2014. For registration and further information on the courses, please consult our web site or contact Kerstin Fuhrmeister (70896 - language.training@cern.ch).

  17. General and professionnal French courses

    CERN Multimedia

    2013-01-01

    The next session will take place from 27 January to 4 April 2014. These courses are open to everyone working on the CERN site and to their spouses.   Oral Expression This course is aimed at students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. The next session will take place from 27 January to 4 April 2014. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. The next session will take place from 27 January to 4 April 2014. For registration and further information on the courses, please consult our web site or contact Kerstin Fuhrmeister (70896 - language.training@cern.ch).

  18. Fast breeder reactors: Experience and trends. V. 2

    International Nuclear Information System (INIS)

    1986-01-01

    The IAEA Symposium on ''Fast Breeder Reactors: Experience and Future Trends'' was held, at the invitation of the Government of France, in Lyons, France, on 22-26 July 1985. It was hosted by the French Commissariat a l'energie atomique and Electricite de France. The purpose of the Symposium was to review the experience gained so far in the field of LMFBRs, taking into account the constructional, operational, technological, economic and fuel cycle aspects, and to consider the developmental trends as well as the international co-operation in fast breeder reactor design and utilization. The Symposium was attended by almost 400 participants (340 participants, 35 observers and 20 journalists) from 25 countries and five international organizations. More than 80 papers were presented and discussed during six regular sessions and four poster sessions. A separate abstract was prepared for each of these papers

  19. Hierarchies of Authenticity in Study Abroad: French from Canada versus French from France?

    Science.gov (United States)

    Wernicke, Meike

    2016-01-01

    For many decades, Francophone regions in Canada have provided language study exchanges for French as a second language (FSL) learners within their own country. At the same time, FSL students and teachers in Canada continue to orient to a native speaker standard associated with European French. This Eurocentric orientation manifested itself in a…

  20. The French energy programme

    International Nuclear Information System (INIS)

    Bohnen, U.

    1980-01-01

    The challenge of the oil crisis made French energy policy react chiefly by means of a programme for the rapid expansion of nuclear energy which has become unparalleled because of its systematic realization. The following article gives a survey of this programme and its political preconditions. The French energy programme deserves special attention as the utilization of nuclear energy in France including all related activities has reached a more advanced stage than in most other countries. The effects and requirements connected with such an extensive programme which can therefore be investigated with the help of the French example migth be of importance also for other countries in a similar way. (orig./UA) [de

  1. Gluon polarization in the proton: Constraints at low x from the measurement of the double longitudinal spin asymmetry for forward-rapidity hadrons with the PHENIX detector at RHIC

    Science.gov (United States)

    McKinney, Cameron Palmer

    In the 1980s, polarized deep inelastic lepton-nucleon scattering experiments revealed that only about a third of the proton's spin of ½ h is carried by the quarks and antiquarks, leaving physicists with the puzzle of how to account for the remaining spin. As gluons carry roughly 50% of the proton's momentum, it seemed most logical to look to the gluon spin as another significant contributor. However, lepton-nucleon scattering experiments only access the gluon helicity distribution, Delta g, through effects on the quark distributions via scaling violations. Constraining Deltag through scaling violations requires experiments that together cover a large range of Q 2. Such experiments had been carried out with unpolarized beams, leaving g(x) (the unpolarized gluon distribution) relatively well-known, but the polarized experiments have only thus far provided weak constraints on Deltag in a limited momentum fraction range. With the commissioning in 2000 of the Relativistic Heavy Ion Collider, the first polarized proton-proton (pp) collider, and the first polarized pp running in 2002, the gluon distributions could be accessed directly by studying quark-gluon and gluon-gluon interactions. In 2009, data from measurements of double longitudinal spin asymmetries, ALL, at the STAR and PHENIX experiments through 2006 were included in a QCD global analysis performed by Daniel de Florian, Rodolfo Sassot, Marco Stratmann, and Werner Vogelsang (DSSV), yielding the first direct constraints on the gluon helicity. The DSSV group found that the contribution of the gluon spin to the proton spin was consistent with zero, but the data provided by PHENIX and STAR was all at mid-rapidity, meaning Delta g was constrained by data only a range in x from 0.05 to 0.2, leaving out helicity contributions from the huge number of low- x gluons. A more recent analysis by DSSV from 2014 including RHIC data through 2009 for the first time points to significant gluon polarization at intermediate

  2. The Hidden Lincoln in French Opinion

    Directory of Open Access Journals (Sweden)

    Jacques Portes

    2016-05-01

    Full Text Available Abraham Lincoln has never served as a model for French politicians. He was indeed compared to Carnot, the organizer of the French Revolutionary wars. But when Clemenceau led France in WWI, when De Gaulle stood for France’s independence in WWII, nobody thought of comparing them to Lincoln. This essay analyzes French public opinion during the American Civil War with a focus on Lincoln, based on a study of the few French books published between 1860 and 1865 on the US, diaries, a sample of conservative and republican daily papers, weekly reviews and illustrated newspapers.

  3. Crisis in the French nuclear industry

    International Nuclear Information System (INIS)

    Nectoux, F.

    1991-02-01

    This report discusses the economics of the French nuclear power industry. It considers the dominant position of nuclear power in the French energy system, stresses the scale and causes of the current (1990) economic crisis and dispels the popular misconceptions on the cost efficiency of the French programme. The evidence is based on widely available French documents and articles. The report begins by looking at the background of nuclear power in France then discusses the problem of overcapacity, the technical problems and fall in load factors, generating costs and electricity prices and finally, strategic issues are considered. (UK)

  4. The French energy policy

    International Nuclear Information System (INIS)

    Maillard, D.; Baulinet, Ch.; Lajoinie, A.

    2001-01-01

    France has to face strong energy challenges: a heavy energy bill, increasing supplies risk, no decreasing CO 2 emissions, deregulation of energy markets, nuclear controversy etc.. In consequence, the French government has defined a voluntaristic energy policy with a better balance between the development of renewable energies and the mastery of energy and without renouncing the advantages of nuclear energy. In parallel, the electric power and natural gas industries have to cope with the deregulation of energy markets and the resulting competition. This issue of 'Energies et Matieres Premieres' newsletter comprises 3 articles. The first one gives a general presentation of the French energy policy ('mobilizing our margins of manoeuvre without renouncing our stakes'): challenges of the energy policy (greenhouse effect, security of supplies, long-term worldwide energy context, European integration, nuclear contestation), stakes for France (evolution of production structure, advantages of the French energy status), renewable energies and energy saving, long-term view of the nuclear industry, managing together the dynamism of competition and the advantages of public utilities. The second article entitled 'energy for everybody: a challenge for the 21. century' is a reprint of the introduction of the information report registered on January 31, 2001 by the commission of production and exchanges of the French national assembly. The third article is a reprint of the summary of conclusions and recommendations of the IEA about the French energy policy. (J.S.)

  5. Minor actinides transmutation potential: state of art for GEN IV sodium cooled fast reactors

    International Nuclear Information System (INIS)

    Buiron, Laurent

    2015-01-01

    In the frame of the R and D program relative to the 1991 French act on nuclear waste management, fast neutron systems have shown relevant characteristics that meet both requirements on sustainable resources management and waste minimization. They also offer flexibility by mean of burner or breeder configurations allowing mastering plutonium inventory without significant impact on core safety. From the technological point of view, sodium cooled fast reactor are considered in order to achieve mean term industrial deployment. The present document summaries the main results of R and D program on minor actinides transmutation in sodium fast reactor since 2006 following recommendation of the first part of the 1991 French act. Both homogeneous and heterogeneous management achievable performances are presented for 'evolutionary' SFR V2B core as well as low void worth CFV core for industrial scale configurations (1500 MWe). Minor actinides transmutation could be demonstrated in the ASTRID reactor with the following configurations: - a 2%vol Americium content for the homogeneous mode, - a 10%vol Americium content for the heterogeneous mode, without any substantial modification of the main core safety parameters and only limited impacts on the associated fuel cycle (manufacturing issues are not considered here). In order to achieve such goal, a wide range of experimental irradiations driven by transmutation scenarios have to be performed for both homogeneous and heterogeneous minor actinides management. (author) [fr

  6. Societal risk as seen by the French public

    International Nuclear Information System (INIS)

    Karpowicz-Lazreg, C.; Mullet, E.

    1993-01-01

    Mean risk magnitude judgments expressed by French students on 90 hazardous activities are reported and compared with findings on American, Hungarian, and Norwegian samples. In many respects, rating of perceived risk in the French sample is highly comparable to rating in American subjects. American and French people tend to share the same preoccupations to the same extent. The only major differences concern hallucinatory drugs and oral contraceptives. The Norwegians and French ratings differ much more. Norwegians and French people generally have the same preoccupations (which make Norwegian ratings the best predictor of French ratings) but not to the same extent. The French are much more concerned with a whole series of activities connected to violence, the implementation of high technology or agricultural technology. However, like the Norwegians, the French are extremely concerned about the spread of hallucinogenic drugs. The Hungarian and French ratings differ on practically all instances, except on basic activities or substances in all industrialized nations (caffeine, motorcycles, ...). Differences were observed within the French sample itself. Women more than men consider that home appliances in general and large-scale public transportation are potentially dangerous. Science students more than art students tend to fear a certain number of medical techniques and a certain number of toxic substances (e.g., smoking). 7 refs., 1 tab

  7. Nutrient Intakes of the Enlisted Personnel Aboard the USS Saratoga Before and After Implementing ’Fast Food’ to the Food Service System.

    Science.gov (United States)

    1982-05-01

    intakes. In 1978, vitamin A fortified milk shakes (dry base) and vitamin C fortified extruded French fried potatoes and vitamin C fortified non...dry base) and vitamin C fortified extruded French fried potatoes and vitamin C fortified non-carbonated beverages were provided with the "Fast Food...identification of any unusual food items, and assignment of each food item as a component of either a meal or between-meal snack . The LAIR Nutrient Factor File

  8. Practising French grammar a workbook

    CERN Document Server

    Dr Roger Hawkins; Towell, Richard

    2015-01-01

    This new edition of Practising French Grammar offers a set of varied and accessible exercises for developing a practical awareness of French as it is spoken and written today. The lively examples and authentic texts and cartoons have been updated to reflect current usage. A new companion website provides a wealth of additional interactive exercises to help consolidate challenging grammar points. Practising French Grammar provides concise summaries of key grammatical points at the beginning of each exercise, as well as model answers to the exercises and translations of difficult words, making i

  9. Language Training - French Training

    CERN Multimedia

    HR Department

    2008-01-01

    General and Professional French Courses The next session will take place from 26 January to 3rd April 2009. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Writing Professional Documents in French The next session will take place from 26 January to 3rd April 2009. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF For further information and registration, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Nathalie Dumeaux Tel. 78144 mailto:nathalie.dumeaux@cern.ch

  10. Language Training - French Training

    CERN Multimedia

    HR Department

    2009-01-01

    General and Professional French Courses The next session will take place from 26 January to 3rd April 2009. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Writing Professional Documents in French The next session will take place from 26 January to 3rd April 2009. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF For further information and registration, please consult our Web pages: http://cern.ch/Training or contact Mrs. Nathalie Dumeaux : Tel. 78144. Nathalie Dumeaux Tel. 78144 mailto:nathalie.dumeaux@cern.ch

  11. Presentation of the selected French libraries and the French library system

    Directory of Open Access Journals (Sweden)

    Moja Kotar

    2007-01-01

    Full Text Available The Selected French libraries (Bibliotheque nationale de France, Bibliotheque publique d’information, multimedia library of the Cité des sciences et de l’industrie as well as Paris public libraries are presented in the article. France does not have a union catalogue at the national level, therefore libraries use different platforms for shared cataloguing and compile more union catalogues. According to their needs, French libraries join into consortia for the acquisition of electronic resources, which can be either geographically or thematically delimited or formed by the institutions of the same status. The author believes that the Slovenian library network works well considering much smaller budget for culture and higher education in comparison with France. To improve its performance, more funds would have to be allocated and higher reputation of the library profession achieved, comparable to the situation in France. Digitization of resources is the area where the Slovenian librarianship lags most behind the French one.

  12. The reprocessing of fast reactor fuels - the TOR project

    International Nuclear Information System (INIS)

    Calame-Longjean, A.; Le Bouhellec, J.; Schwob, Y.

    1982-01-01

    A description is given of development work on the proposed new French facility for the reprocessing of fast reactor fuel. This is the TOR facility (Traitement des Oxydes Rapides). Block diagrams give details of the TOR project as a whole and of the main line and R and D line of the TOR 1 facility which is a new works devoted to the head of the process. Modifications to existing plant which will form the TOR 2 and TOR 3 facilities are also described. (U.K.)

  13. Are Fast Food “Trans-Fat” Claims True? An Infraspec VFA-IR Spectrometer Analysis of Trans-fat content in select food items purchased from Long John Silver’s

    Directory of Open Access Journals (Sweden)

    Sharron Jenkins

    2014-10-01

    Full Text Available Studies linking high trans-fat diets to coronary heart disease (CHD have prompted the need to regulate, limit, or completely ban trans-fat from all commercial food products, including fast foods. Many U.S. fast food chains now claim that their food items, particularly French fries, have "no trans-fat". In a previous study, our lab tested the validity of trans-fat claims made by several popular fast food restaurants by experimentally determining the %trans-fat in oil extracted from fast food French fries. In some cases, the trans-fat content was nearly twice as high as the amount reported by the restaurant in their literature. Long John Silver's, for example, reported a trans-fat content of 25% for their French fries, while our lab actually found over 40% trans-fat. The purpose of this study is to broaden our study of Long John Silver's trans-fat claims by analyzing a variety of their food items and comparing our findings with the %trans-fat reported by the restaurant literature (nutrition fact tables. Variable Filter Array (VFA IR spectroscopy was used to assess the trans-fat content of oil extracted from food samples. Our preliminary findings suggest that nearly every food item under study contained considerably more trans-fat than the amount reported in the restaurant’s literature.

  14. Switches to English during French Service Encounters: Relationships with L2 French Speakers' Willingness to Communicate and Motivation

    Science.gov (United States)

    McNaughton, Stephanie; McDonough, Kim

    2015-01-01

    This exploratory study investigated second language (L2) French speakers' service encounters in the multilingual setting of Montreal, specifically whether switches to English during French service encounters were related to L2 speakers' willingness to communicate or motivation. Over a two-week period, 17 French L2 speakers in Montreal submitted…

  15. Acoustic Waves: A Route to Enhance Sodium Fast Reactor Safety

    International Nuclear Information System (INIS)

    Jeannot, Jean-Philippe; Baque, François; Cavaro, Matthieu; Gastaldi, Olivier; Lhuilier, Christian; Massacret, Nicolas; Moriot, Jérémy; Paumel, Kévin; Vandergaegen, Matthias; Rodriguez, Gilles

    2013-01-01

    Improvement to prevent core meltdown and to provide a more robust safety demonstration → Safety objectives: - A level of safety at least equivalent to EPR’s level, - Consolidation of the defence-in-depth principle, - A more robust safety demonstration than those of the Phenix and Superphenix reactor. Acoustic techniques: - Low attenuation by the sodium medium - High velocity of US wave (2289 m.s-1 at 550°C) →

  16. Revis(iting French palatalization

    Directory of Open Access Journals (Sweden)

    Ali Tifrit

    2016-06-01

    Full Text Available This paper explores the diachrony of French and reconsiders the classical analysis of French palatalizations. It is widely admitted that the transition from Latin dorsal stops to French palatal fricatives is triggered by an external palatalizing object which affects the constitution of the targeted consonant. While this analysis can satisfyingly explain the palatalization of dorsals before /i/, it makes the palatalization before /a/, which occurred a few centuries later, completely opaque. Revising the internal structure and the melody used to describe segments (Government Phonology 2.0 – Pöchtrager 2006 allows us to give a unified analysis of both palatalizations: whether /i/ or /a/, the vocalic environment is indeed the trigger, as it interferes with the structure of dorsals and lead to internal changes. However, while /i/ adds palatality to the consonant, /a/, by its lack of melody (Pöchtrager & Živanović 2010, leads to an internal reconfiguration of the dorsal, which already contains . In other words, we face two kinds of palatalization: an external one and an internal one. Furthermore, our analysis takes the intermediate stages from Latin dorsals to French palatals into consideration and attested dialectal variations observed in Northern France.

  17. Commissioning the world's first commercial scale FBR at Creys-Malville

    International Nuclear Information System (INIS)

    Mergyu, A.

    1988-01-01

    The Super-Phenix fast breeder reactor start-up program is described. Content of certain stages of start-up is presented. Problems on start-up period and ways of their solutions are discussed. Results of start-up tests are generalized, the character of difficulties, and equipment failures is described

  18. Axial heterogeneous core concept applied for super phoenix reactor

    International Nuclear Information System (INIS)

    Batista, J.L.; Renke, C.A.C.; Waintraub, M.; Santos Bastos, W. dos; Brito Aghina, L.O. de.

    1991-11-01

    Always maintaining the current design rules, this paper presents a parametric study on the type of axial heterogeneous core concept (CHA), utilizing a core of fast reactor Super Phenix type, reaching a maximum thermal burnup rate of 150000 M W d/t and being managed in single batch. (author)

  19. 7 CFR 993.6 - Non-French prunes.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 8 2010-01-01 2010-01-01 false Non-French prunes. 993.6 Section 993.6 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Order Regulating Handling Definitions § 993.6 Non-French prunes. Non-French prunes means prunes commonly...

  20. Constraining ΔG at low-x with Double Longitudinal Spin Asymmetries for Forward Hadrons in PHENIX

    Science.gov (United States)

    McKinney, Cameron; Phenix Collaboration

    2013-10-01

    Recent global analyses that include polarized p+p data from RHIC through 2009 suggest for the first time a positive contribution of the gluon polarization, ΔG , to the overall proton spin. The data sets included in the analysis constrain Δg (x) in the range 0 . 05 double helicity asymmetry in hadron production at large pseudorapidity, with a dominant contribution from collisions between a high-momentum quark and a low-momentum gluon. At PHENIX, we measure cluster ALL at large pseudorapidity (3 . 1 Piston Calorimeter (MPC). The majority of the clusters (> 80 %) come from π0 decay where the photon showers in the calorimeter overlap. Simulations using the event generator PYTHIA have shown that measuring forward π0's can access Δg (x) for x 10-2 for inclusive π0's or down to x 10-3 for the dihadron channel. Here, we present the status of ALL measurements in the MPC at √{ s } = 500 GeV from the 2011 through 2013 runs. This data will help to provide stronger constraints on the form of Δg (x) in ongoing global analyses.

  1. Sodium components cleaning status in the Italian fast reactor program

    Energy Technology Data Exchange (ETDEWEB)

    De Luca, B [CNEN-RIT/MAT - Laboratorio Sviluppo Processi - C.S.N. Cassacia, Rome (Italy); Labanti, V [CNEN-DRV, Bologna (Italy); Mennucci, M [NIRA, Genoa (Italy)

    1978-08-01

    As a consequence of the Italian Fast Reactor Development, mainly aimed to the PEC project and to the participation in the French Superphenix project, it is of increasing importance to set up a reliable method for specific reactor components and related test loops. The first problem was the cleaning of the PEC fuelling machine. In order to perform the routine maintenance of the machine an alcohol cleaning method based on the use of 2-butoxyethanol-NN dimethylformamide mixture has been proposed.

  2. Commercial French in a Liberal Arts Setting.

    Science.gov (United States)

    Abrate, Jayne

    Drury College (Missouri) has developed a commercial French course that is practical, situation-oriented, and provides instruction in correspondence and translation. The course is considered part of the cultural segment of the French program. It enrolls majors in business, French, and a variety of other disciplines, and emphasizes contextual…

  3. Language Training: French

    CERN Multimedia

    Françoise Benz

    2004-01-01

    If you wish to participate in one of the following courses, please discuss with your supervisor and apply electronically directly from the course description pages that can be found on the Web at: http://www.cern.ch/Training/ or fill in an 'application for training' form available from your Divisional Secretariat or from your DTO (Divisional Training Officer). Applications will be accepted in the order of their receipt.General and Professional French Courses The next session will take place from 26 April to 02 July 2004. These courses are open to all persons working on the Cern site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz: Tel. 73127. Writing Professional Documents in French The next session will take place from 26 April to 02 July 2004. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF (for 8 students) For further information and registra...

  4. General and Professional French Courses

    CERN Document Server

    HR Department

    2011-01-01

    The next session will take place from 10th of October to 16th of December 2011. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://hr-training.web.cern.ch/hr-training/ or contact Kerstin Fuhrmeister (kerstin.fuhrmeister@cern.ch) Oral Expression This course is aimed for students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. Suitable candidates should contact Kerstin Fuhrmeister (70896) or Martine Zuffi (73483) in order to arrange an appointment for a test. The next session will take place from 10th of October to 16th of December 2011. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. Suitable candidates should contact Kerstin Fuhrmeister (70896) or Martine Zuffi (73483) in order to arr...

  5. General and Professional French Courses

    CERN Multimedia

    HR Department

    2011-01-01

    The next session will take place from 30th of January to 5th of April 2012. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://hr-training.web.cern.ch/hr-training/ or contact Kerstin Fuhrmeister (kerstin.fuhrmeister@cern.ch) Oral Expression This course is aimed for students with a good knowledge of French who want to enhance their speaking skills. Speaking activities will include discussions, meeting simulations, role-plays etc. Suitable candidates should contact Kerstin Fuhrmeister (70896) or Martine Zuffi (73483) in order to arrange an appointment for a test. The next session will take place from 30th of January to 5th of April 2012. Writing professional documents in French These courses are designed for non-French speakers with a very good standard of spoken French. Suitable candidates should contact Kerstin Fuhrmeister (70896) or Martine Zuffi (73483) in order to arrange an ...

  6. The First Asymmetry Measurements in High-Energy Polarized Proton-Nucleus Collision at PHENIX-RHIC

    Directory of Open Access Journals (Sweden)

    Nakagawa Itaru

    2017-01-01

    Full Text Available The single spin asymmetries in very forward neutron production had been first observed about a decade ago at RHIC in transversely polarized proton + proton collision at √s = 200 GeV. Although neutron production near zero degrees is well described by the one-pion exchange (OPE framework, the OPE appeared to be not satisfactory to describe the observed analyzing power AN. The absorptive correction to the OPE generates the asymmetry as a consequence of a phase shift between the spin flip and non-spin flip amplitudes. However the amplitude predicted by the OPE is too small to explain the large observed asymmetries. Only the model which introduces interference between major pion and small a1-Reggeon exchange amplitudes has been successful in reproducing the experimental data. During RHIC Run-15, RHIC delivered polarized proton collisions with Au and Al for the first time, enabling the exploration of the mechanism of transverse single-spin asymmetries with nuclear collisions. A very striking A-dependence was discovered in very forward neutron production at PHENIX in transversely polarized proton + nucleus collision at √s = 200 GeV. Such a dependence has not been predicted from the existing framework which has been succesful in proton + proton collision. In this report, experimental and theoretical efforts are discussed to disentangle the mysterious A-dependence in the very forward neutron asymmetry.

  7. The acquisition of French in multilingual contexts

    CERN Document Server

    Guijarro-Fuentes, Pedro; Müller, Natascha

    2015-01-01

    This volume brings together new research from different theoretical paradigms addressing the acquisition of French as a second language. It focuses on the acquisition of French in combination with different languages and enriches our understanding of the particularities of French and the role of language combinations in the acquisition process.

  8. Colloquial French the complete course for beginners

    CERN Document Server

    Demouy, Valérie

    2015-01-01

    Colloquial French: The Complete Course for Beginners has been carefully developed by an experienced teacher to provide a step-by-step course to French as it is written and spoken today. Combining a clear, practical and accessible style with a methodical and thorough treatment of the language, it equips learners with the essential skills needed to communicate confidently and effectively in French in a broad range of situations. No prior knowledge of the language is required. Colloquial French is exceptional; each unit presents a wealth of grammatical points that are reinforced with a wide range

  9. 4th French-German Conference on Optimization

    CERN Document Server

    Zowe, Jochem; Hiriart-Urruty, Jean-Baptiste; Lemarechal, Claude

    1988-01-01

    This volume contains a collection of 23 papers presented at the 4th French-German Conference on Optimization, hold at Irsee, April 21 - 26, 1986. The conference was aUended by ninety scientists: about one third from France, from Germany and from third countries each. They all contributed to a highly interesting and stimulating meeting. The scientifique program consisted of four survey lectures of a more tutorical character and of 61 contributed papers covering almost all areas of optimization. In addition two informal evening sessions and a plenary discussion on further developments of optimization theory were organized. One of the main aims of the organizers was to indicate and to stress the increasing importance of optimization methods for almost all areas of science and for a fast growing number of industry branches. We hope that the conference approached this goal in a certain degree and managed to continue fruitful discussions between -theory­ and -applications-. Equally important to the official contri...

  10. The French R and D programme for fast reactor fuel reprocessing

    International Nuclear Information System (INIS)

    Auchapt, P.; Bourgeois, M.; Calame-Longjean, A.; Miquel, P.; Sauteron, J.

    1979-01-01

    The process employed is the Purex process adapted to the specific case of fast breeder reactor fuels. The results achieved have demonstrated that the aqueous method can be applied to these fuels: nearly ten years of operation in the ATl workshop which reprocesses RAPSODIE fuels, and the good results obtained at the Marcoule pilot facility on large batches of fuel attest to this achievement. The CEA effort continues principally on extrapolation to industrial scale, thanks mainly to experiments conducted on industrial prototypes and to the launching of the TOR project, which will, as of 1984, allow reprocessing of FBR fuels on a significant scale, and which will provide extensive additional resources for R and D activities

  11. Slang Usage of French by Young Americans.

    Science.gov (United States)

    Ensz, Kathleen Y.

    1985-01-01

    Describes reactions of native French speakers to usage of French slang by young American students. French-speaking participants rated 30 tape-recorded slang expressions. Their reactions were evaluated in relation to the sex, profession, age, and residence of the respondents. Results show attitudes critical of the use of slang in general. (SED)

  12. French participation in the world energy council

    International Nuclear Information System (INIS)

    Carouge, Ch.; Roussely, F.; Francony, M.; Ailleret, F.; Bosseboeuf, D.; Moisan, F.; Villaron, Th.

    1999-01-01

    The Revue de l'Energie is presenting the most influential French interventions at the 17. Congress of the World Energy Council held in September 1998 in Houston, (USA). These represent only part of French participation in the congress since a total of 16 individuals from France took part in the various sessions. Their presentations cover very varied topics and are one of the things that testify to the interest that our energy industries have in the works and operations of the WEC. Some other figures also bear witness to this interest: 184 French congress members, which is one of the largest delegations after that of the United States, the host country of the congress; 11 technical presentation, covering a wide range of subjects: from the nuclear reactor of the future to the use of bagasse (cane trash) for the production of electricity, from the underground storage of natural gas to the production of extra-heavy crude petroleum. The technical exhibition associated to the Congress was a great success and there again the French presence was able to make its mark: five exhibitors were gathered in the France of 600 m 2 , the most sizeable non-American national area.But French participation in the work of the WEC is not limited to congresses. The French Energy Council [Conseil francais de l'Energie] is careful to ensure its presence both in the formal proceedings of the WEC and within the studies undertaken under its three-year programme. This active French presence is also essential in order to defend the official English-French bilingualism of the World Energy Council. In spite of the good will of the organizers and the support of the general secretary's office in London, the Houston Congress showed how difficult it was to maintain the use of the French language on English-speaking territory. This is a difficult task, one that has to be undertaken anew each time, but one that France and other French-speaking nations have decided to pursue to the end. (authors)

  13. TEACHING AND LEARNING OF FRENCH: IMPERATIVE FOR ...

    African Journals Online (AJOL)

    Prof

    It is important to note that, the teaching of French was introduced into the ... subjects like English to the detriment of French language is a proof of that .... To encourage teachers to lead the learners to use French language as a tool for .... professionals, thereby placing Nigeria at a disadvantage in terms of job creation.

  14. Report: Immersion French at Meriden Junior School

    Science.gov (United States)

    Esposito, Marie-Josee

    2006-01-01

    In this article, the author describes the French immersion program at Meriden Junior School, an Anglican school for girls from pre-Kindergarten to Year 12 in Sydney. Four teachers (one of whom is the coordinator) and three assistants are involved in the program. They include six French native speakers and one non-French-born teacher who speaks…

  15. French electric power balance sheet 2009

    International Nuclear Information System (INIS)

    Lartigau, Thierry; Riere, Alexia

    2010-01-01

    The mission of RTE, the French electricity Transportation grid, a public service assignment, is to balance the electricity supply and demand in real time. This report presents RTE's technical results for the year 2009: key figures of the French electricity consumption, lowering of the French power generation, decrease of trade balance at borders but still positive, continuation of RTE's investments for the improvement of the grid performance. New RTE's infrastructures, electricity quality data, and the evolution of market mechanisms are presented in appendixes

  16. Effectiveness of a Heritage Educational Program for the Acquisition of Oral and Written French and Tahitian in French Polynesia

    Science.gov (United States)

    Nocus, Isabelle; Guimard, Philippe; Vernaudon, Jacques; Paia, Mirose; Cosnefroy, Olivier; Florin, Agnes

    2012-01-01

    The research examines the effects of a bilingual pedagogical program (French/Tahitian) on the acquisition of oral and written French as well as the Tahitian language itself in primary schools in French Polynesia. 125 children divided into an experimental group (partially schooled in Tahitian for 300 min per week) and a control group (schooled in…

  17. Swelling of structural materials in fast neutron reactors

    International Nuclear Information System (INIS)

    Seran, J.L.

    1983-06-01

    The physical origin of swelling in irradiated materials and the main parameters acting on swelling of SS 316 are examined: temperature, neutron dose, dose rate, chemical composition, strain hardening. Results obtained, in Rapsodie and Phenix reactors, with fuel cans and with the hexagonal tube containing the fuel pins are analyzed and compared with results found in litterature. In conclusion hot swelling of SS 316 is too important at high doses and is will be replaced by austenitic steels stabilized by Ti and ferritic steels or high nickel steels with structural hardening [fr

  18. Report of Inquiry Commission (1) on Superphenix and the fast neutron reactor system. Vol. 2. Hearings

    International Nuclear Information System (INIS)

    Galley, Robert; Bataille, Christian

    1998-01-01

    This document is a two-volume report, made on behalf of the Inquiry Commission of French National Assembly, concerning the issue of Superphenix and the fast neutron reactor system. The first volume contains the report while the second presents the accounts of 27 hearings in the Inquiry Commission. Questions concerning the technical aspects, costs of decommissioning operations, environment and social impacts, etc, are addressed and discussed with officials implied in nuclear safety, environment protection, science and technology, trade unions, education, atomic energy agency, military applications, industry and commerce. The conclusions drawn from these hearings were synthesized in the volume one of the report submitted to the French National Assembly by the Inquiry Commission

  19. The french electric power evaluation 2005

    International Nuclear Information System (INIS)

    2006-01-01

    This document takes stock on the french electric power situation for the year 2005. It provides information on the consumption the trade, the production, the french market and the RTE (Electric power transport network) infrastructure. (A.L.B.)

  20. French in the XX Century: Development Tendencies

    Directory of Open Access Journals (Sweden)

    Taisiya I. Skorobogatova

    2017-06-01

    Full Text Available This article is devoted to the disclosure of changes that occurred in the French language in the XX century. The task of the authors is to present the main features characteristic of the French language of the 20th century, taking into account external history and to give their perspective assessment. World wars, the development of communication tools and the creation of new technologies, the strengthening of cultural and economic ties between France and other countries of the world had a significant impact on the evolution of the French language. Important results of the development of the French language in the period under review include: fixing a new phoneme [ŋ] in the consonantial system of the French language; enrichment of the lexical system at the expense of internal resources and at the expense of other languages; strengthening the dynamics of the development of the non-literary part of the language; increase in the number of syntactic Anglicisms. In general, the authors of the article attempted to give a detailed answer to the question: if there was the impoverishment of the French language in the twentieth century.

  1. French bank mergers and acquisitions performance

    Directory of Open Access Journals (Sweden)

    Houda Ben Said

    2017-11-01

    Full Text Available In this paper, we empirically investigate the impact of mergers and acquisitions on French bank performance. Performance is measured by potential gains in efficiency and value creation. We first analyzed efficiency using the data envelopment analysis (DEA under input oriented with variable returns to scale to obtain the efficiency scores. Second, we analyzed the impact on French bank value creation following mergers-acquisitions operations of a set of control variables (model 1 and explicative variables measuring strategic similarities between bidders and targets (model 2. The sample studied is composed of French bank mergers-acquisitions happening between 1996 and 2006 and implying one of the 14 greatest French banking groups. Empirical result showed that mergers and acquisitions have been traduced by an improvement in the overall efficiency by 17.82% and a shareholder value reduction by 5.14%

  2. Appropriating Written French: Literacy Practices in a Parisian Elementary Classroom

    Science.gov (United States)

    Rockwell, Elsie

    2012-01-01

    In this article, I examine French language instruction in an elementary classroom serving primarily children of Afro-French immigrants in Paris. I show that a prevalent French language ideology privileges written over oral expression and associates full mastery of written French with rational thought and full inclusion in the French polity. This…

  3. French regulations

    International Nuclear Information System (INIS)

    Ballereau, P.

    1998-01-01

    In this issue are given the new French regulations relative to radiation protection of temporary personnel, the licensing to release gaseous and liquid wastes and the licensing granted to thirty two laboratories using beta and gamma decay radioisotopes. (N.C.)

  4. [From the French Society of Plastic and Reconstructive Surgery to the French Society of Plastic Reconstructive and Aesthetic Surgery].

    Science.gov (United States)

    Glicenstein, J

    2004-04-01

    (The) 3rd December 1952, 11 surgeons and other specialists found the French Society of Plastic and Reconstructive Surgery (SFCPR) which was officially published on (the) 28 September 1953. The first congress was during October 1953 and the first president as Maurice Aubry. The first secretary was Daniel Morel Fatio. The symposiums were after about three of four times each year and the thematic subjects were initially according the reconstructive surgery. The review "Annales de chirurgie plastique" was free in 1956. The members of the Society were about 30 initially, but their plastic surgery in the big hospitals at Paris and other big towns in France. The "specialty" of plastic surgery was created in 1971. On "syndicate", one French board of plastic reconstructive and aesthetic surgery, the increasing of departments of plastic surgery were the front of increasing of the plastic surgery in French and of the number of the French Society of Plastic Reconstructive surgery (580 in 2003). The French Society organized the International Congress of Plastic Surgery in 1975. The society SFCPR became the French Society of plastic reconstruction and Aesthetic Surgery (SFCPRE) in 1983 and the "logo" (front view) was in the 1994 SOF.CPRE.

  5. [Primary management of endometrial carcinoma. Joint recommendations of the French society of gynecologic oncology (SFOG) and of the French college of obstetricians and gynecologists (CNGOF)].

    Science.gov (United States)

    Querleu, D; Darai, E; Lecuru, F; Rafii, A; Chereau, E; Collinet, P; Crochet, P; Marret, H; Mery, E; Thomas, L; Villefranque, V; Floquet, A; Planchamp, F

    2017-12-01

    The management of endometrial carcinoma is constantly evolving. The SFOG and the CNGOF decided to jointly update the previous French recommendations (Institut national du cancer 2011) and to adapt to the French practice the 2015 recommendations elaborated at the time of joint European consensus conference with the participation of the three concerned European societies (ESGO, ESTRO, ESMO). A strict methodology was used. A steering committee was put together. A systematic review of the literature since 2011 has been carried out. A first draft of the recommendations has been elaborated, with emphasis on high level of evidence. An external review by users representing all the concerned discipines and all kinds of practice was completed. Three hundred and four comments were sent by 54 reviewers. The management of endometrial carcinoma requires a precise preoperative workup. A provisional estimate of the final stage is provided. This estimation impact the level of surgical staging. Surgery should use a minimal invasive approach. The final pathology is the key of the decision concerning adjuvant therapy, which involves surveillance, radiation therapy, brachytherapy, or chemotherapy. The management algorithms allow a fast, state of the art based, answer to the clinical questions raised by the management of endometrial cancer. They must be used only in the setting of a multidisciplinary team at all stages of the management. Copyright © 2017 Elsevier Masson SAS. All rights reserved.

  6. Dyslexia in a French-Spanish bilingual girl: behavioural and neural modulations following a visual attention span intervention.

    Science.gov (United States)

    Valdois, Sylviane; Peyrin, Carole; Lassus-Sangosse, Delphine; Lallier, Marie; Démonet, Jean-François; Kandel, Sonia

    2014-04-01

    We report the case study of a French-Spanish bilingual dyslexic girl, MP, who exhibited a severe visual attention (VA) span deficit but preserved phonological skills. Behavioural investigation showed a severe reduction of reading speed for both single items (words and pseudo-words) and texts in the two languages. However, performance was more affected in French than in Spanish. MP was administered an intensive VA span intervention programme. Pre-post intervention comparison revealed a positive effect of intervention on her VA span abilities. The intervention further transferred to reading. It primarily resulted in faster identification of the regular and irregular words in French. The effect of intervention was rather modest in Spanish that only showed a tendency for faster word reading. Text reading improved in the two languages with a stronger effect in French but pseudo-word reading did not improve in either French or Spanish. The overall results suggest that VA span intervention may primarily enhance the fast global reading procedure, with stronger effects in French than in Spanish. MP underwent two fMRI sessions to explore her brain activations before and after VA span training. Prior to the intervention, fMRI assessment showed that the striate and extrastriate visual cortices alone were activated but none of the regions typically involved in VA span. Post-training fMRI revealed increased activation of the superior and inferior parietal cortices. Comparison of pre- and post-training activations revealed significant activation increase of the superior parietal lobes (BA 7) bilaterally. Thus, we show that a specific VA span intervention not only modulates reading performance but further results in increased brain activity within the superior parietal lobes known to housing VA span abilities. Furthermore, positive effects of VA span intervention on reading suggest that the ability to process multiple visual elements simultaneously is one cause of successful

  7. Radioactivity in French bottled waters

    Energy Technology Data Exchange (ETDEWEB)

    Loyen, J.; Brassac, A.; Augeray, C.; Fayolle, C.; Gleizes, M. [Institut de Radioprotection et de Surete Nucleaire - IRSN (France)

    2014-07-01

    As IRSN is considered as a reference laboratory for radioactivity measurements, French health ministry and French nuclear safety authority asked IRSN to carry out a study in order to get a fresh and complete status of radiological water quality of French bottled waters. The study was carried out during 12 months in 2012. A total of 142 bottled waters samples were analyzed (75 spring waters and 67 natural mineral waters). The laboratories of IRSN were in charge of: - systematic measurement of radioactivity following requirements of the French health ministry (Circulaire du 13/06/2007) regarding the monitoring and management of sanitary risk linked to the presence of radionuclides in drinking waters (natural mineral waters excepted). - systematic uranium mass concentration determination; - a few radon-222 gas measurements for waters in glass bottles. This study is a flash assessment of radiological characteristics of French bottled waters, at the analysis date for the sample received. It was done in informative way and was not done for regulatory control purposes.. This study has shown that: - all bottled waters analyzed have a tritium activity concentration lower than the quality reference value of 100 Bq/l of the French regulation; - More than 105 bottled waters analyzed (80% of the springs waters and 70% of natural mineral waters received) have a gross alpha activity concentration lower than the guideline value of 0,1 Bq/l of the French regulation; - All bottled waters analyzed have a residual gross beta activity concentration lower than the guideline value of 1 Bq/l of the French regulation; - All bottled waters analyzed have a uranium mass concentration lower than the provisory guideline value of 30 μg/l of the WHO for drinking waters; - radon-222 was only significantly measured once upon 6 glass bottled waters with a value far below the reference value of 100 Bq/l of the future European Directive on drinking waters. For 32 bottled waters with gross alpha

  8. developing french for specific purposes in the nigerian university ...

    African Journals Online (AJOL)

    Ada

    Following the changing role of the French Language from a vehicle of French culture to a vehicle of Science, Technology, Commerce and Diplomacy, the teaching of French as a foreign language (FFL) around the world has shifted emphasis from literary studies to what has come to be known as French for Specific Purposes ...

  9. Harmonizing the prototypes concerning the fast reactors of 4. generation

    International Nuclear Information System (INIS)

    Anon.

    2008-01-01

    In january 2008, an agreement was signed between the Japan Atomic Energy Agency (JAEA), the American Department of Energy (DOE) and the French Atomic Energy Commission, in order to harmonize the projects of the 3 countries for the development of prototypes of sodium-cooled fast reactors. This cooperation concerns the following issues: -) the purpose of the prototypes, -) common set of safety rules, -) technical innovations for reducing construction, operating and maintenance costs, and -) information exchange about the level of power, the type of nuclear fuels and the time schedule of these prototypes. (A.C.)

  10. High temperature fission chambers. Fast breeder reactor research and development program

    International Nuclear Information System (INIS)

    Berlin, C.; Perrigueur, J.C.

    1984-04-01

    Development of a high temperature fission chamber and experimentations of measuring channels (detectors and electronic devices) in similar conditions as those of power plants: development of measuring channels (impulses and current) of the Super Phenix neutronic measures auxiliary system, development of a measuring channel with impulses for the surveillance system of the clad failures, based on integrated detectors, and development of a fission chamber for experimentations in similar conditions as in Superphenix [fr

  11. Progress in the development of the neutron flux monitoring system of the French GEN-IV SFR: simulations and experimental validations [ANIMMA--2015-IO-98

    Energy Technology Data Exchange (ETDEWEB)

    Jammes, C.; Filliatre, P.; De Izarra, G. [CEA, DEN, DER, Instrumentation, Sensors and Dosimetry Laboratory, Cadarache, F-13108 Saint-Paul-lez-Durance, (France); Elter, Zs.; Pazsit, I. [Chalmers University of Technology, Department of Applied Physics, Division of Nuclear Engineering, SE-412 96 Goteborg, (Sweden); Verma, V.; Hellesen, C.; Jacobsson, S. [Division of Applied Nuclear Physics, Uppsala University, Box 516, SE-75120 Uppsala, (Sweden); Hamrita, H.; Bakkali, M. [CEA, DRT, LIST, Sensors and Electronic Architecture Laboratory, Saclay, F-91191 Gif Sur Yvette, (France); Chapoutier, N.; Scholer, A-C.; Verrier, D. [AREVA NP, 10 rue Juliette Recamier F-69456 Lyon, (France); Cantonnet, B.; Nappe, J-C. [PHONIS France S.A.S, Nuclear Instrumentation, Avenue Roger Roncier, B.P. 520, F-19106 Brive Cedex, (France); Molinie, P.; Dessante, P.; Hanna, R.; Kirkpatrick, M.; Odic, E. [Supelec, Department of Power and Energy System, F-91192 Gif Sur Yvette, (France); Jadot, F. [CEA, DEN, DER, ASTRID Project Group, Cadarache, F-13108 Saint-Paul-lez-Durance, (France)

    2015-07-01

    The neutron flux monitoring system of the French GEN-IV sodium-cooled fast reactor will rely on high temperature fission chambers installed in the reactor vessel and capable of operating over a wide-range neutron flux. The definition of such a system is presented and the technological solutions are justified with the use of simulation and experimental results. (authors)

  12. Concept and experimental studies on fuel and target for minor actinides and fission products transmutation

    Energy Technology Data Exchange (ETDEWEB)

    Prunier, C; Guerin, Y [CEA Centre d` Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d` Etudes des Combustibles; Salvatores, M [CEA Centre d` Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Direction des Reacteurs Nucleaires; Zaetta, A [CEA Centre d` Etudes de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d` Etudes des Reacteurs

    1994-12-31

    High activity long-lived radionuclides in nuclear wastes, namely minor actinides (americium and neptunium) are in large amount generated by current nuclear reactive. The destruction of these radionuclides is a part of the French SPIN (Partitioning and Burning) program consistent with the determination to send a minimum amount of harmful products for final storage. Transmutation concepts are defined for neptunium and americium taking into account fuel cycle strategies. Neptunium destruction does not pose any major problems. It`s a by-product of uranium consumption, as plutonium and in despite of a slight gamma activity due to the protactinium 233 it`s quite easy to handle. Diluting neptunium in the mixed oxide fuels (MOX) should not be an obstacle for fabrication, in-pile behaviour and reprocessing either. Consequently we make the proposal of homogeneous mode of neptunium in MOX which should be soon explored in the experimental OSIRIS reactor and in the Phenix and Superphenix reactors. The analysis is more complex for the multi isotope americium. Its destruction is difficult because of gamma radioactivity which complicates fabrication. Experiments in Phenix and calculation showed that Phenix reactor offers a good potential for americium incineration, but similar data do not exist for PWR. It will remain a well known difficulty for fabrication and reprocessing. In this case we have to put a real new face to the fabrication flow-sheet of americium compounds and we propose to develop the heterogeneous mode. Targets choice are defined in term of: -safety, considering fuel reaction with cladding and water sodium, -transmutation rate, limited by target behaviour, in FR`s (Phenix), PWR`s (OSIRIS) and HFR (Petten), -reprocessing, checking the solubility of such targets by Purex process. So, at the beginning of our program the account has been on improving fuel and targets properties related to safety and fuel cycle. (authors). 4 figs.

  13. French electric power balance sheet 2010

    International Nuclear Information System (INIS)

    Lartigau, Thierry; Riere, Alexia

    2011-01-01

    The mission of RTE, the French electricity Transportation grid, a public service assignment, is to balance the electricity supply and demand in real time. This report presents RTE's technical results for the year 2010: increase of RTE's investments and safety expenses for adapting the grid to the new electricity industry stakes and to meteorological hazards, decrease of power cuts frequency, rise of the French power consumption, strong increase of winter consumption peaks, increase of the French power generation, increase of the positive trade balance. New RTE's infrastructures, electricity quality data, and the evolution of market mechanisms are presented in appendixes

  14. Snakebites in French Guiana: Conclusions of an international symposium.

    Science.gov (United States)

    Kallel, Hatem; Hommel, Didier; Mehdaoui, Hossein; Megarbane, Bruno; Resiere, Dabor

    2018-05-01

    A workshop on epidemiology and management of snakebites in French Guiana was performed at Cayenne, French Guiana from September 15 to September 16, 2017, under the auspices of the French Regional Health Agency (ARS) and the Pan American Health Organization (PAHO). The activity was attended by experts from France (Angers, Martinique, French Guiana, Guadeloupe, and Paris), Costa Rica, Brazil, Saint Lucia, and Surinam. The epidemiology, clinical manifestations, clinical grading and the management of snakebite in French Guiana were discussed. The conclusions of this symposium illustrated the urgent need to ensure accessibility of effective and safe polyvalent viperid antivenom in French Guiana. Finally, the results of this symposium have forged ties based on mutual goals and objectives. Copyright © 2018 Elsevier Ltd. All rights reserved.

  15. Fast neutron spectrometry and dosimetry; Spectrometrie et dosimetrie des neutrons rapides

    Energy Technology Data Exchange (ETDEWEB)

    Blaize, S; Ailloud, J; Mariani, J; Millot, J P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    We have studied fast neutron spectrometry and dosimetry through the recoil protons they produce in hydrogenated samples. In spectrometric, we used nuclear emulsions, in dosimetric, we used polyethylene coated with zinc sulphide and placed before a photomultiplier. (author)Fren. [French] Nous avons etudie la spectrometrie et la dosimetrie des neutrons rapides en utilisant les protons de recul qu'ils produisent dans une matiere hydrogenee. En spectrometrie, nous avons employe des emulsions nucleaires, en dosimetrie, du polyethylene recouvert de sulfure de zinc place devant un photomultiplicateur. (auteur)

  16. Ethno-linguistic peculiarities of French Canadian and English ...

    African Journals Online (AJOL)

    When English Canadian and French Canadian phraseology is compared, the greater role of religion in the French Canadian community is evident, rather than in English Canadian; the influence of the Canadian variant of the English language on the Canadian variant of French is clearly expressed. With all the differences, ...

  17. Prospects of the French offshore wind power market

    International Nuclear Information System (INIS)

    Anon.

    2011-12-01

    This market study about the French offshore wind power industry presents: 1 - the bases of the offshore wind power market: wind turbine operation principle, foundations and scale change; 2 - business model of offshore wind power projects: logistical, technical and financial challenges, cost structure and profitability of projects (investment, power generation costs, incentive mechanisms), project development time; 3 - European and French regulatory framework: the energy/climate package, the French 'Grenelle de l'Environnement' commitments for the development of renewable energies; 4 - start up of the French offshore wind power market: the onshore wind power market looking for growth relaying, the lateness of the offshore market, outlines of the call for bids and of the first phase launching (schedule, selected sites and candidates), market development stakes and opportunities; 5 - offshore wind power overview in Europe - lessons for the French market prospects: status of the European market (installed power/country, projects in progress), European leaders of the market (analysis of the British, Danish and German markets successful takeoff), specificities of the French market (are all favourable conditions present?); 6 - takeoff of the French market - what opportunities on the overall value chain?: front-end of the industry (manufacturers and component suppliers: industry structure, competition, R and D, subcontractors in France), back-end of the industry (developers/operators: sector analysis, ambitions, alliances, competences), specific French know-how in offshore installation and connection of wind turbines (reconversion of harbour areas, re-positioning of shipbuilding industry). (J.S.)

  18. The French electricity report 2009

    International Nuclear Information System (INIS)

    2010-01-01

    RTE is the company responsible for running the French electricity transmission system. It is a public service operator, tasked with operating, maintaining and developing the high and extra high voltage network. It guarantees the reliability and proper operation of the power network. These missions were entrusted to it by the Law of 10 February 2000. With 100,000 km of lines between 63,000 and 400,000 volts and 45 cross-border lines, the network operated by RTE is the biggest in Europe. In 2008, RTE posted turnover of euros 4,221 m and currently employs around 8,500 staff. RTE, by virtue of the missions entrusted to it by the Law of 10 February 2000, is the central player in the French power system. For the purpose of maintaining the real time balance between supply and demand, and managing contractual relations with customers connected to its network, RTE monitors all the electrical energy that enters and leaves the public transmission system. Through its management of the 45 interconnection lines linking France with its neighbours, RTE also tracks all import and export data, on behalf of players in the French and European electricity market. RTE constantly records and examines data provided by all market players. Using the data, monthly and annually, it publishes exhaustive figures for the French power system (demand, generation, imports and exports), which offer the only truly accurate reflection of the real state of the sector's economy. This report presents these figures for the year 2009. Contents: 1 - French electricity demand down by 1.6% on 2008; 2 - A drop in French electricity generation; 3 - The balance of cross-border exchanges falls, but remains positive; 4 - RTE continues to invest in a robust network capable of keeping up with developments in the electricity industry; 5 - Appendix 1: New infrastructures on the RTE network in 2009; 6 - Appendix 2: Electricity quality; 7 - Appendix 3: Mature market mechanisms

  19. French electricity results 2002

    International Nuclear Information System (INIS)

    2002-01-01

    RTE, the manager of the French power system, announces a high increase in electricity exports to the other countries of the European Union in 2002. In France, the year 2002 was marked by stable power consumption, but a noteworthy increase in generation due to the rise of exports. In 2002, the RTE network conveyed 512.3 billion kWh (TWh) versus 503.1 billion kWh (TWh) in 2001, an increase of 1.8%. Overall French exports made considerable strides forward from 72.9 TWh in 2001 to 80.6 TWh in 2002, i.e. 10.6% more than in 2001. On the other hand, overall French imports fell substantially, from 4.4 TWh in 2001 to 3.8 TWh in 2002, or a drop of about 14%. In all, the export balance came to 76.8 TWh in 2002, versus 68.5 TWh in 2001, i.e. a rise of 12%. On Sunday, 22 December 2002, the historical record of the capacity export balance with a value of 13,277 MW, up 2.2%, was bettered. The particularly mild weather conditions in 2002 led to a drop in heating-related consumption, evaluated at 7 billion kWh compared with the prior year. A slight upturn in industrial consumption was to be noted, from 92.7 TWh in 2001 to 93.2 TWh in 2002, i.e. a growth of 0.5%. Total French consumption thus rose in 2002 to 448.7 TWh. Total consumption, adjusted for climate contingencies, showed a rise of 1.6% in 2002. French power producers showed an increase of nearly 2% and the first wind farm was connected to the power transmission network. French electricity output came to 532.9 TWh in 2002, a growth of 1.9%. This increase is divided up between nuclear generation, up 4%, and conventional thermal generation, on the rise by 15.3%. The substantial share of thermal generation can be explained by a correlative drop in hydro generation (less 16.6% compared with 2001) mainly due to extremely low water availability observed during the first months of the year. With 415.5 TWh in output, nuclear power plants provided 78% of French generation, fossil-fired power plants 9.9% with an output of 52.9 TWh

  20. French Modular Impoundment: Final Cost and Performance Evaluation

    Energy Technology Data Exchange (ETDEWEB)

    Drown, Peter [French Development Enterprises, LLC, North Billerica, MA (United States); French, Bill [French Development Enterprises, LLC, North Billerica, MA (United States)

    2017-05-17

    This report comprises the Final Cost and Performance Report for the Department of Energy Award # EE0007244, the French Modular Impoundment (aka the “French Dam”.) The French Dam is a system of applying precast modular construction to water control structures. The “French Dam” is a term used to cover the construction means/methods used to construct or rehabilitate dams, diversion structures, powerhouses, and other hydraulic structures which impound water and are covered under FDE’s existing IP (Patents # US8414223B2; US9103084B2.)

  1. French Romanticism and Napoleon's "Geometric Men."

    Science.gov (United States)

    Cole, Robert A.

    1982-01-01

    French intellectual thought changed during the Napoleonic Era. The effects of the Enlightenment philosophers, the French Revolution, the Industrial Revolution, and Romanticism on the development of Napoleon's philosophical outlook are used to illustrate the changes occurring in France as a whole in the early nineteenth century. (AM)

  2. Opening of the French gas market

    International Nuclear Information System (INIS)

    Syrota, J.

    2002-01-01

    A report on the opening of the French gas market has been established, on the request of both the French minister of economy, finances and industry and the state secretary of industry, as expressed in their respective letters addressed to the president of the commission of electric power regulation (CRE). This report follows the step report on the opening of the French gas market published on January 15, 2002. It presents a status of the French gas market since August 2000, date of the enforcement of the European Union directive 98/30/CE, and expresses some recommendations about the main questions that should fall into the field of the future gas regulation. This report was elaborated before the project of law relative to the energy markets and published on October 24, 2002. These recommendations will have to be adapted to the dispositions of the law. This article presents some excerpts of the synthesis report. (J.S.)

  3. French civil law aspects of international sales of oil

    International Nuclear Information System (INIS)

    Moquet, A.

    1992-01-01

    There is not in France, as in London and New York, and organised trade market for crude oil and oil products. French law does not apply to oil futures negotiated in foreign markets, although solicitation in France for transactions in a foreign market is legal only if that market is approved by the French Minister in charge of Economic Affairs. However, French oil producers do enter into OTC forward and commodity swap agreements. Although most of these agreements are standardised and expressly choose English law and the jurisdiction of the High Court of London for resolution of disputes, fundamental principles of French private international law may impose jurisdiction of a French Commercial Court (in case of bankruptcy of the French party for example) and/or rules of necessary application or public order. (author)

  4. Overview of the FUTURIX-FTA Irradiation Experiment in the Phénix Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Heather J.M. Chichester; Steve L. Hayes; Kenneth J. McClellan; Jean-Luc Paul; Marc Masson; Stewart L. Voit; Fabienne Delage

    2015-09-01

    The Advanced Fuels Campaign utilizes the Advanced Test Reactor (ATR) for most of its irradiation testing. Cadmium-shrouded baskets are used in ATR to modify the neutron spectrum to simulate a fast reactor environment for the fuel. FUTURIX-FTA is an irradiation experiment conducted in the Phenix fast reactor in France. Results from FUTURIX-FTA and irradiation tests in ATR using identical fuel compositions will be compared to identify and evaluate any differences in fuel behavior due to differences in the irradiation source.

  5. Gabonese French Dictionaries: Survey and Perspectives*

    African Journals Online (AJOL)

    Gabonese French Dictionaries: Survey and Perspectives. 257 ... be regarded, according to Gouws (2007: 314), as externally motivated products. .... Fair attention is given to different style or normative levels, i.e. .... differs enough from standard French to be regarded as a new emerging lan- ..... Tous les leaders des par-.

  6. "So She Has Been Educated by a Vulgar, Silly, Conceited French Governess!" Social Anxieties, Satirical Portraits, and the Eighteenth-Century French Instructor

    Science.gov (United States)

    Hegele, Arden

    2011-01-01

    Maria Edgeworth's pedagogical short stories "Mademoiselle Panache" (1800, 1801) and "The Good French Governess" (1801) portray contrasting French instructors, and illustrate a transformation in English girls' education in French at the end of the eighteenth century. While "Mademoiselle Panache" looks back to the…

  7. Gastrointestinal illnesses among French forces deployed to Djibouti: French military health surveillance, 2005-2009.

    Science.gov (United States)

    Ollivier, Lénaïck; Decam, Christophe; Pommier de Santi, Vincent; Darar, Houssein Y; Dia, Aïssata; Nevin, Remington L; Romand, Olivier; Bougère, Jacques; Deparis, Xavier; Boutin, Jean-Paul

    2010-10-01

    Despite an increase in foreign tourism and in the numbers of foreign military personnel deployed to Djibouti, little is known about the risk of gastrointestinal illness in this country in eastern Africa. To assess risk and to describe common features of gastrointestinal illnesses, reports of illness derived from military health surveillance data collected during 2005-2009 among French service members deployed to Djibouti were reviewed. Diarrhea was the most common problem; it had an annual incidence ranging from 260 to 349 cases per 1,000 person-years. The risk was higher among soldiers deployed short-term (four months) than among soldiers deployed long-term (two years). This five-year review of French health surveillance data documents a significant burden of diarrhea among French soldiers in Djibouti. The identification of factors associated with risk may permit efficient targeting of interventions to reduce morbidity from gastrointestinal illness.

  8. In-service inspection of nuclear power plants

    International Nuclear Information System (INIS)

    Asty, M.; Saglio, R.

    1984-10-01

    The French Commissariat a l'Energie Atomique (Atomic Energy Commission) developed two new non destructive control techniques, focused ultrasonics and multi-frequency eddy currents, which have been shown to allow a better detection and characterization of defects. We present here some of the in-service inspection devices which have been designed for field application of these techniques on the PWR reactors built by EDF, inspection devices of the PWR steam generator tubing and the now developing specific device for main tank and helicoidal tubing steam generator of Super-Phenix 1 [fr

  9. End stage renal disease in French Guiana (data from R.E.I.N registry): South American or French?

    Science.gov (United States)

    Rochemont, Dévi Rita; Meddeb, Mohamed; Roura, Raoul; Couchoud, Cécile; Nacher, Mathieu; Basurko, Célia

    2017-06-30

    End-Stage renal disease (ESRD) causes considerable morbidity and mortality, and significantly alters patients' quality of life. There are very few published data on this problem in the French Overseas territories. The development of a registry on end stage renal disease in French Guiana in 2011 allowed to describe the magnitude of this problem in the region for the first time. Using data from the French Renal Epidemiology and Information Network registry (R.E.I.N). Descriptive statistics on quantitative and qualitative variables in the registry were performed on prevalent cases and incident cases in 2011, 2012 and 2013. French Guiana has one of the highest ESRD prevalence and incidence in France. The two main causes of ESRD were hypertensive and diabetic nephropathies. The French Guianese population had a different demographic profile (younger, more women, more migrants) than in mainland France. Most patients had at least one comorbidity, predominantly (95.3%) hypertension. In French Guiana dialysis was initiated in emergency for 71.3% of patients versus 33% in France (p < 0.001). These first results give important public health information: i) End stage renal disease has a very high prevalence relative to mainland France ii) Patients have a different demographic profile and enter care late in the course of their renal disease. These data are closer to what is observed in the Caribbean or in Latin America than in Mainland France.

  10. Planning and developing the French nuclear programme

    International Nuclear Information System (INIS)

    Carle, R.

    1983-01-01

    Since France has been compelled to free itself from the domination of oil, it has undertaken a nuclear programme capable of providing for nearly one third of its energy needs by 1990. Some years after the first oil crisis, a good part of the battle has already been won: 22 reactor units of 900 MW each have been connected to the grid and account for 40% of the electricity produced in France, while 12 other 900 MW units, together with the first 1300 MW units, are under construction. Nuclear power has thus become an industrial reality possessed of the tools appropriate for the whole fuel cycle, which has managed to cope with costs and meet deadlines, and has developed a safe and reliable product. With these positive results despite inevitable incidents the French nuclear industry has come of age. There are, however, handicaps which remain to be overcome: high investment costs, operating constraints and continuing doubt on the part of the public. The efforts deployed in these three spheres are beginning to bear fruit. As a result, implementation of the French nuclear programme is being continued, albeit at a slower rate, for the aim is no longer to replace oil by nuclear power as soon as possible, but rather to keep up with the rise in consumption. In pursuing its nuclear efforts, France will henceforth be stressing progress in terms of quality, which can still be achieved in terms of increased reliability (incorporation of feedback), better economic return (initiation of a new series known as ''N4''), easier operation (improvement of the man-machine interface) and also more independence. The ''frenchification'' of the light-water reactor has from the beginning been seen as one of the means of achieving this independence. This also applies to mastery of the whole fuel cycle. And finally, fast breeders represent the next stage

  11. REPLACEMENT OF FRENCH CARDS

    CERN Multimedia

    Human Resources Division

    2001-01-01

    The French Ministry of Foreign Affairs has informed the Organization that it is shortly to replace all diplomatic cards, special cards and employment permits ('attestations de fonctions') now held by members of the personnel and their families. Between 2 July and 31 December 2001, these cards are to be replaced by secure, computerized equivalents. A 'personnel office' stamped photocopy of the old cards may continue to be used until 31 December 2001. For the purposes of the handover, members of the personnel must go personally to the cards office (33/1-015), between 8:30 and 12:30, in order to fill a 'fiche individuelle' form (in black ink only), which has to be personally signed by themselves and another separately signed by members of their family, taking the following documents for themselves and members of their families already in possession of a French card : A recent identity photograph in 4.5 cm x 3.5 cm format (signed on the back) The French card in their possession an A4 photocopy of the same Fre...

  12. Language Training - French Training

    CERN Document Server

    2007-01-01

    General and Professional French Courses The next session will take place from 29 January to 30 March 2007. These courses are open to all persons working on the CERN site, and to their spouses. For registration and further information on the courses, please consult our Web pages: http://cern.ch/Training or contact Mrs. Benz : Tel. 73127. Writing Professional Documents in French The next session will take place from 29 January to 30 March 2007. This course is designed for people with a good level of spoken French. Duration: 30 hours Price: 660 CHF (for 8 students) For further information and registration, please consult our Web pages:   http://cern.ch/Training or contact Mrs. Benz : Tel. 73127. Writing Professional Documents in English The next session will take place from January to June 2007 (break at Easter). This course is designed for people with a good level of spoken English. Duration: 30 hours Price: 660 CHF (for 8 students) Timetable will be fixed after discussion with the students. For registratio...

  13. Static feedback model for neutronic and thermodynamic simulation of fast reactors

    International Nuclear Information System (INIS)

    Waintraub, M.; Jachic, J.

    1985-01-01

    It is analysed the variation of the microscopic cross sections with neutronic spectra and temperature of materials for reactors such as SUPER-PHENIX. It was realized a parametric study of each spectral component, where the influence of each isotope was analysed separately. To include the Doppler effect and other important effects, neutronic and thermodynamic calculations in an iterative form were done allowing to determine neutron temperatures for fuel, structural material and coolant. (M.C.K.) [pt

  14. The French nuclear program: national prospects, international cooperation

    International Nuclear Information System (INIS)

    Lacoste, A.; Joint-Lambert, V.; Breard, G.; Jolly, B.; Durret, L.F.; Capus, G.; Lebastard, G.; Ouzounian, G.; Bouteille, F.; Appell, B.; Peyran, J.C.; Monnet, F.; Caoul, A.

    1998-01-01

    This issue, with a foreword by Christian Pierret, the French Secretary of State of Industry, is bilingual (French/English). It gives a thorough overview of the French nuclear industry: present situation, expected evolutions; some typical cooperations with others countries throughout the world. It contains a leaflet in which advertisers give some information about their products and services. (author)

  15. Strategies for improved French-language health services

    Science.gov (United States)

    Gauthier, Alain P.; Timony, Patrick E.; Serresse, Suzanne; Goodale, Natalie; Prpic, Jason

    2015-01-01

    Abstract Objective To identify strategies to improve the quality of health services for Francophone patients. Design A series of semistructured key informant interviews. Setting Northeastern Ontario. Participants A total of 18 physicians were interviewed. Ten physicians were interviewed in French, 7 physicians were women, and 10 physicians were located in urban communities. Methods Purposive and snowball sampling strategies were used to conduct a series of semistructured key informant interviews with family physicians practising in communities with a large Francophone population. Principles of grounded theory were applied, guided by a framework for patient-professional communication. Results were inductively derived following an iterative data collection–data analysis process and were analyzed using a detailed thematic approach. Main findings Respondents identified several strategies for providing high-quality French-language health services. Some were unique to non–French-speaking physicians (eg, using appropriate interpreter services), some were unique to French-speaking physicians (eg, using a flexible dialect), and some strategies were common to all physicians serving French populations (eg, hiring bilingual staff or having pamphlets and posters in both French and English). Conclusion Physicians interviewed for this study provided high-quality health care by attributing substantial importance to effective communication. While linguistic patient-to-physician concordance is ideal, it might not always be possible. Thus, conscious efforts to attenuate communication barriers are necessary, and several effective strategies exist. PMID:26505060

  16. The French Fast Reactor Program - Innovations in Support to Higher Standards

    International Nuclear Information System (INIS)

    Gauché, François

    2013-01-01

    • From the experience of ASTRID first phase of conceptual design studies (2010-2012), two remarks can be made: → Higher requirements in safety and operability lead to higher costs that cannot be fully recovered by advances in technology. This puts additional pressure on the next phases of the design to optimize the design and to keep the costs to the minimum. → There is a clear link between the level of safety that can be achieved and the maturity of the technology, i.e. the experience accumulated in R&D, design, construction, operation and decommissioning of past reactors. In the field of fast neutron reactors, this gives a strong advantage to the sodium technology, because strengths and weaknesses are well mastered. • Meeting the high requirements set for ASTRID and serving R&D needs of innovative options will require increased industrial and international collaboration

  17. Management of neutropenic patients in the intensive care unit (NEWBORNS EXCLUDED) recommendations from an expert panel from the French Intensive Care Society (SRLF) with the French Group for Pediatric Intensive Care Emergencies (GFRUP), the French Society of Anesthesia and Intensive Care (SFAR), the French Society of Hematology (SFH), the French Society for Hospital Hygiene (SF2H), and the French Infectious Diseases Society (SPILF).

    Science.gov (United States)

    Schnell, David; Azoulay, Elie; Benoit, Dominique; Clouzeau, Benjamin; Demaret, Pierre; Ducassou, Stéphane; Frange, Pierre; Lafaurie, Matthieu; Legrand, Matthieu; Meert, Anne-Pascale; Mokart, Djamel; Naudin, Jérôme; Pene, Frédéric; Rabbat, Antoine; Raffoux, Emmanuel; Ribaud, Patricia; Richard, Jean-Christophe; Vincent, François; Zahar, Jean-Ralph; Darmon, Michael

    2016-12-01

    Neutropenia is defined by either an absolute or functional defect (acute myeloid leukemia or myelodysplastic syndrome) of polymorphonuclear neutrophils and is associated with high risk of specific complications that may require intensive care unit (ICU) admission. Specificities in the management of critically ill neutropenic patients prompted the establishment of guidelines dedicated to intensivists. These recommendations were drawn up by a panel of experts brought together by the French Intensive Care Society in collaboration with the French Group for Pediatric Intensive Care Emergencies, the French Society of Anesthesia and Intensive Care, the French Society of Hematology, the French Society for Hospital Hygiene, and the French Infectious Diseases Society. Literature review and formulation of recommendations were performed using the Grading of Recommendations Assessment, Development and Evaluation system. Each recommendation was then evaluated and rated by each expert using a methodology derived from the RAND/UCLA Appropriateness Method. Six fields are covered by the provided recommendations: (1) ICU admission and prognosis, (2) protective isolation and prophylaxis, (3) management of acute respiratory failure, (4) organ failure and organ support, (5) antibiotic management and source control, and (6) hematological management. Most of the provided recommendations are obtained from low levels of evidence, however, suggesting a need for additional studies. Seven recommendations were, however, associated with high level of evidences and are related to protective isolation, diagnostic workup of acute respiratory failure, medical management, and timing surgery in patients with typhlitis.

  18. Foreign direct investments into French real estate

    OpenAIRE

    BRIZARD, Arthur

    2013-01-01

    The purpose of this thesis is to draw the global trend of Foreign Direct Investments (FDI) in the French real estate market since 2008 and to understand foreign investors’ behavior and the incentives which urge them to invest in French property market. This study relies on the numerous yearly reports released by consulting and real estate companies and gives an overview of FDI since 2008. From a legal point of view, the French property market is extremely organized. Acquiring, holding and sel...

  19. French how to speak and write it

    CERN Document Server

    Lemaître, Joseph

    1978-01-01

    Probably the most delightful, useful, and comprehensive elementary book available for learning spoken and written French, either with or without a teacher. Includes colloquial French conversations as well as grammar, vocabulary, and idiom studies.

  20. The French civilian nuclear: connections and stakes

    International Nuclear Information System (INIS)

    2010-01-01

    This document (18 power point slides) gives an overview of the French civilian nuclear industry and research and development: importance of the nuclear power generation in France, excellence of the education in nuclear sciences, organization of the nuclear connection (CEA, Areva, EDF, IRSN), the role of the French International Nuclear Agency (AFNI), the requirements for a renewal of human resources (French and foreign engineers) in the field of nuclear energy, the degree course for a diploma, examples of engineer and university diplomas, the educational networks in various regions of France, presentation of the Institut National des Sciences et Techniques Nucleaires (Nuclear Sciences and Techniques National Institute) and its master degrees, organization of the French education system in nuclear sciences with strong relations with the research and development programs