The Experts below are selected from a list of 300 Experts worldwide ranked by ideXlab platform
J R Murray - One of the best experts on this subject based on the ideXlab platform.
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open_quotes Framatome technologies vitrification process close_quotes
1996Co-Authors: S P Hellman, L E Draus, J J Guiroy, J R MurrayAbstract:One of the major difficulties encountered in vitrifying low- and medium-activity radioactive wastes is ensuring that volatile components, such as cesium (Cs), are integrated into the requisite waste glass matrix and not carried over, in vapor or particulate form, into the off-gas system. The inability to retain these volatile components within the glass matrix can result in radioactive carryover into the off-gas system requiring separate treatment and/or extraction processes. This difficulty is of particular concern in vitrifying wastes that generate large amounts of gas or vapor when broken down by heat. In these cases, the gases or vapors generated may transport the volatile particles or vapors into the off-gas system before they can be integrated into the glass matrix of even before they come in contact with the liquid glass medium, such as in the {open_quotes}cold-cap{close_quotes} vitrification process. This phenomenon is further aggravated if the waste is in the form of a fine, easily entrained powder or contains excessive moisture, such as in spent resins in bead or powder form, sludges, or concentrates.
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{open_quotes}Framatome technologies` vitrification process{close_quotes}
1996Co-Authors: S P Hellman, L E Draus, J J Guiroy, J R MurrayAbstract:One of the major difficulties encountered in vitrifying low- and medium-activity radioactive wastes is ensuring that volatile components, such as cesium (Cs), are integrated into the requisite waste glass matrix and not carried over, in vapor or particulate form, into the off-gas system. The inability to retain these volatile components within the glass matrix can result in radioactive carryover into the off-gas system requiring separate treatment and/or extraction processes. This difficulty is of particular concern in vitrifying wastes that generate large amounts of gas or vapor when broken down by heat. In these cases, the gases or vapors generated may transport the volatile particles or vapors into the off-gas system before they can be integrated into the glass matrix of even before they come in contact with the liquid glass medium, such as in the {open_quotes}cold-cap{close_quotes} vitrification process. This phenomenon is further aggravated if the waste is in the form of a fine, easily entrained powder or contains excessive moisture, such as in spent resins in bead or powder form, sludges, or concentrates.
Norbert Nicaise - One of the best experts on this subject based on the ideXlab platform.
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Evolution of Design Methodologies for Next Generation of Reactor Pressure Vessels and Extensive Role of Thermal-Hydraulic Numerical Tools
Nuclear Technology, 2005Co-Authors: Serge Bellet, Nicolas Goreaud, Norbert NicaiseAbstract:The thermal-hydraulic design of the first pressurized water reactors was mainly based on an experimental approach, with a large series of tests on the main equipment [control rod guide tubes, reactor pressure vessel (RPV) plenums, etc.] to check performance.Development of computational fluid dynamics codes and computers now allows for complex simulations of hydraulics phenomena. Provided adequate qualification, these numerical tools are an efficient means to determine hydraulics in the given design and to perform sensitivities for optimization of new designs. Experiments always play their role, first for qualification and then for validation at the last stage of the design. The design of the European Pressurized Water Reactor (EPR), jointly developed by Framatome ANP, Electricite de France (EDF), and the German utilities, is based on both hydraulics calculations and experiments handled in a complementary approach.This paper describes the collective effort launched by Framatome ANP and EDF on hydraulics calculations for the RPV of the EPR. It concerns three-dimensional calculations of RPV inlets, including the cold legs, the RPV downcomer and lower plenum, and the RPV upper plenum up to and including the hot legs. It covers normal operating conditions but also accidental conditions such as pressurized thermal shock in a small-breakmore » loss-of-coolant accident. Those hydraulics studies have provided much useful information for the mechanical design of RPV internals.« less
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Evolution of the Thermal Hydraulics Design Methodologies for the European Pressurized Reactor (EPR) Vessel
Emerging Technology in Fluids Structures and Fluid Structure Interactions: Volume 2 Dynamics of Explosive Detonation Materials and Structures Structur, 2004Co-Authors: Serge Bellet, Nicolas Goreaud, Norbert NicaiseAbstract:The thermal-hydraulic design of the first PWR’s was mainly based on an experimental approach, with a large series of test on the main equipment (control rod guide tubes, RPV plenums ...), to check its performances. Development of CFD-codes and computers now allows for complex simulations of hydraulic phenomena. Provided adequate qualification, these numerical tools are efficient means to determine hydraulics in the given design, and to perform sensitivities for optimization of new designs. Experiments always play their role, first for qualification, and for validation at the last stage of the design. The design of the European Pressurized water Reactor (EPR), jointly developed by Framatome-ANP, EDF the German Utilities (GU), is based on both hydraulic calculations and experiments, handled This paper describes the collective effort launched by Framatome-ANP and EDF, on hydraulic calculations for the Reactor Pressure Vessel (RPV) of the EPR reactor. It concerns 3D-calculations of RPV-inlet including cold legs, RPV-downcomer and lower plenum, RPV-upper plenum up to and including hot legs. It covers normal operating conditions, but also accidental conditions as PTS (Pressurized Thermal Shock) in small break loss of coolant accident (SB-LOCA). Those hydraulic studies have provided numerous useful information for the mechanical design of RPV-internals.Copyright © 2004 by ASME
S P Hellman - One of the best experts on this subject based on the ideXlab platform.
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open_quotes Framatome technologies vitrification process close_quotes
1996Co-Authors: S P Hellman, L E Draus, J J Guiroy, J R MurrayAbstract:One of the major difficulties encountered in vitrifying low- and medium-activity radioactive wastes is ensuring that volatile components, such as cesium (Cs), are integrated into the requisite waste glass matrix and not carried over, in vapor or particulate form, into the off-gas system. The inability to retain these volatile components within the glass matrix can result in radioactive carryover into the off-gas system requiring separate treatment and/or extraction processes. This difficulty is of particular concern in vitrifying wastes that generate large amounts of gas or vapor when broken down by heat. In these cases, the gases or vapors generated may transport the volatile particles or vapors into the off-gas system before they can be integrated into the glass matrix of even before they come in contact with the liquid glass medium, such as in the {open_quotes}cold-cap{close_quotes} vitrification process. This phenomenon is further aggravated if the waste is in the form of a fine, easily entrained powder or contains excessive moisture, such as in spent resins in bead or powder form, sludges, or concentrates.
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{open_quotes}Framatome technologies` vitrification process{close_quotes}
1996Co-Authors: S P Hellman, L E Draus, J J Guiroy, J R MurrayAbstract:One of the major difficulties encountered in vitrifying low- and medium-activity radioactive wastes is ensuring that volatile components, such as cesium (Cs), are integrated into the requisite waste glass matrix and not carried over, in vapor or particulate form, into the off-gas system. The inability to retain these volatile components within the glass matrix can result in radioactive carryover into the off-gas system requiring separate treatment and/or extraction processes. This difficulty is of particular concern in vitrifying wastes that generate large amounts of gas or vapor when broken down by heat. In these cases, the gases or vapors generated may transport the volatile particles or vapors into the off-gas system before they can be integrated into the glass matrix of even before they come in contact with the liquid glass medium, such as in the {open_quotes}cold-cap{close_quotes} vitrification process. This phenomenon is further aggravated if the waste is in the form of a fine, easily entrained powder or contains excessive moisture, such as in spent resins in bead or powder form, sludges, or concentrates.
F Bouteille - One of the best experts on this subject based on the ideXlab platform.
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integration of Framatome anp
Atw. Internationale Zeitschrift für Kernenergie, 2001Co-Authors: W D Krebs, F BouteilleAbstract:The environment of nuclear power has changed greatly in the past few years. Cross-border exchanges of electricity have increased considerably, and more and more free and open markets add to the transparency of the cost situation in power generation. This is the environment in which a new firm is offering the necessary know-how to power companies and nuclear power plant operators. The two leading firms, Framatome and Siemens, have merged their nuclear divisions into Framatome ANP. The new company is active in all areas of nuclear power: new nuclear power plant construction, maintenance, nuclear fuel supply, and nuclear power plant services in Europe, Asia, and America. More than ninety nuclear power plants, which is tantamount to 30 % of the capacity installed worldwide, were built by the two companies, which makes Framatome ANP a leading enterprise for the long-term development of nuclear power. Framatome ANP merges a number of activities characterized by histories and corporate culture of their own within the framework of their respective political, economic, and social environments. The outcome is variety to be combined with extensive experience. Cooperation on the basis of combination of best experience, the exchange of know-how, and the acceptance of differences offers the best opportunities for future developments which, however, also require the best possible preparation. This is underscored by the experience that some 75 % of all company mergers fail to achieve the desired goals of synergy and cost savings.
Christopher France - One of the best experts on this subject based on the ideXlab platform.
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Use of local approach to fracture in reactor pressure vessel structural integrity assessment: synthesis of a cooperative research program between EDF, CEA, Framatome and AEA technology
ASTM Special Technical Publication, 1999Co-Authors: D. Moinereau, J.m. Frund, M.p. Valeta, D. Guichard, Sabin Bhandari, Philippe Joly, Angela Sherry, B. Marini, Jules Brochard, Christopher FranceAbstract:Electricite de France, CEA, Framatome and AEA Technology initiated a cooperative research program on the field of the local approach to cleavage fracture applied to reactor pressure vessels. A total of 120 specimens made from A508 C13 steel were tested at several temperatures ranging from -100°C, -130°C and -170°C. The experimental results were compared and analyzed. Further, a standard procedure to identify the parameters of the Beremin model was proposed.
