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Papers by Michael Futterer

Research paper thumbnail of Synergy between Fast Reactors and Thermal Breeders for Safe, Clean, and Sustainable Nuclear Power

This paper proposes a new approach to nuclear power to achieve a sustainable nuclear future in wh... more This paper proposes a new approach to nuclear power to achieve a sustainable nuclear future in which the transuranic elements or TRUs (neptunium, plutonium and americium) from today's nuclear waste are burned in safe fast reactors such as lead-cooled fast systems. These breed, at the same time, 233 U for use in thermal breeder reactors that are based on the

Research paper thumbnail of Head-End Process for the Reprocessing of Reactor Core Material

Research paper thumbnail of safety assessment and accident management of a water-cooled Pb-17Li test blanket for ITER

Fusion Science and Technology

Research paper thumbnail of Design and transient thermal analysis of a water-cooled Pb-17Li test blanket for ITER

Fusion Science and Technology

Research paper thumbnail of Fragmentation of Coated Particle Fuel Using Welding Techniques

This paper provides results of small-scale feasibility tests concerning fragmentation of HTR fuel... more This paper provides results of small-scale feasibility tests concerning fragmentation of HTR fuel particles in view of their reprocessing and/or separation from their coatings to reduce the waste volume. Tests were performed on small amounts of surrogate fuel particles originally received from CEA France for characterization purposes. Experiments were successfully carried out using standard TIG welding equipment. An acetylene torch test was also conducted. The investigated parameters included: AC/DC, voltage, current, exposure time, electrode type, electrode size, crucible shape etc. In most tests, only 20 new surrogate particles were submitted to an electric arc. After exposure, the intact particles, intact kernels and debris were counted and the number of broken particles was used as performance indicator. Conditions were identified, which fragmented 100% of the treated particles. The energy consumption of the process is small. Three failure mechanisms are suspected, namely thermo...

Research paper thumbnail of Impact of low PRF tritium permeation barriers-on the water cooled lead lithium blanket: A safety analysis

IEEE/NPSS Symposium on Fusion Engineering, 2002

A summary is here presented concerning the first results in evaluating the safety features of the... more A summary is here presented concerning the first results in evaluating the safety features of the European water-cooled lead lithium blanket in which tritium permeation barriers on the external surface of the breeder cooling pipes are not used or, if used, a lower efficiency is required for them. As a consequence, in this design concept, a significant amount of tritium

Research paper thumbnail of JRC-IE's Research on safety of Gen IV systems

The Institute for Energy (IE), one of the seven scientific Institutes of the Joint Research Centr... more The Institute for Energy (IE), one of the seven scientific Institutes of the Joint Research Centre (JRC) of the European Commission, has the mission to provide scientific and technical support for the conception, development, implementation and monitoring of community policies related to energy. To accomplish its mission, IE performs research in the areas of renewable energies, safety and sustainability of nuclear energy for current & future reactor systems, energy techno/economic assessment, and security of energy supply. The Generation IV International Forum (GIF) is a cooperative international endeavour organized to carry out R&D needed to establish the feasibility and performance capabilities of the next generation nuclear energy systems and support the progress towards their realization. The EU, represented by EURATOM and with the JRC as implementing agent, is working together with other GIF partners to perform pre-competitive R&D on key technologies to be implemented in future...

Research paper thumbnail of EU water-cooled Pb-17Li DEMO blanket: fabrication issues and future R&D priorities

Fusion Science and Technology

EU water-cooled Pb-17Li DEMO blanket: fabrication issues and future R&D priorities

Research paper thumbnail of RAPHAEL: The European Union's (Very) High Temperature Reactor Technology Project

Since the late 1990, the European Union (EU) was conducting work on High Temperature Reactors (HT... more Since the late 1990, the European Union (EU) was conducting work on High Temperature Reactors (HTR) confirming their high potential in terms of safety (inherent safety features), environmental impact (robust fuel with no significant radioactive release), sustainability (high efficiency, potential suitability for various fuel cycles), and economics (simplifications arising from safety features). In April 2005, the EU Commission has started

Research paper thumbnail of Raphael, a European Project for the Development of HTR/VHTR Technology for Industrial Process Heat Supply and Cogeneration

Since the late 1990s, the European Commission is supporting the HTR-TN partnership work on the de... more Since the late 1990s, the European Commission is supporting the HTR-TN partnership work on the development of HTR, that resulted in confirming HTR high potential in terms of safety (inherent safety features), environmental impact (robust fuel without significant radioactive release), sustainability (potential suitability for various fuel cycles), and economics (high efficiency, simplifications arising from safety features). In April 2005, a

Research paper thumbnail of High-Temperature Reactor Fuel Technology in the RAPHAEL European Project

Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1, 2008

Research paper thumbnail of High-Temperature Reactor Fuel Technology in the European Projects HTR-F1 and Raphael

Research paper thumbnail of JRC's on-line fission gas release monitoring system in the high flux reactor Petten

Nuclear Engineering and Design, 2012

Research paper thumbnail of European energy policy and the potential impact of HTR and nuclear cogeneration

Nuclear Engineering and Design, 2014

Research paper thumbnail of Long term out-of-pile thermocouple tests in conditions representative for nuclear gas-cooled high temperature reactors

Nuclear Engineering and Design, 2014

Research paper thumbnail of Special edition on HTR 2012 conference

Nuclear Engineering and Design, 2014

Research paper thumbnail of LIBRETTO-3: Performance of tritium permeation barriers under irradiation at the HFR Petten

Journal of Nuclear Materials, 1994

Research paper thumbnail of Water-cooled Pb–17Li test blanket module for ITER: Impact of the structural material grade on the neutronic responses

Journal of Nuclear Materials, 1998

Research paper thumbnail of On the use of tin–lithium alloys as breeder material for blankets of fusion power plants

Journal of Nuclear Materials, 2000

Research paper thumbnail of In-pile tritium-permeation measurements on T91 tubes with double walls or a Fe–Al/Al2O3 coating

Journal of Nuclear Materials, 2000

Research paper thumbnail of Synergy between Fast Reactors and Thermal Breeders for Safe, Clean, and Sustainable Nuclear Power

This paper proposes a new approach to nuclear power to achieve a sustainable nuclear future in wh... more This paper proposes a new approach to nuclear power to achieve a sustainable nuclear future in which the transuranic elements or TRUs (neptunium, plutonium and americium) from today's nuclear waste are burned in safe fast reactors such as lead-cooled fast systems. These breed, at the same time, 233 U for use in thermal breeder reactors that are based on the

Research paper thumbnail of Head-End Process for the Reprocessing of Reactor Core Material

Research paper thumbnail of safety assessment and accident management of a water-cooled Pb-17Li test blanket for ITER

Fusion Science and Technology

Research paper thumbnail of Design and transient thermal analysis of a water-cooled Pb-17Li test blanket for ITER

Fusion Science and Technology

Research paper thumbnail of Fragmentation of Coated Particle Fuel Using Welding Techniques

This paper provides results of small-scale feasibility tests concerning fragmentation of HTR fuel... more This paper provides results of small-scale feasibility tests concerning fragmentation of HTR fuel particles in view of their reprocessing and/or separation from their coatings to reduce the waste volume. Tests were performed on small amounts of surrogate fuel particles originally received from CEA France for characterization purposes. Experiments were successfully carried out using standard TIG welding equipment. An acetylene torch test was also conducted. The investigated parameters included: AC/DC, voltage, current, exposure time, electrode type, electrode size, crucible shape etc. In most tests, only 20 new surrogate particles were submitted to an electric arc. After exposure, the intact particles, intact kernels and debris were counted and the number of broken particles was used as performance indicator. Conditions were identified, which fragmented 100% of the treated particles. The energy consumption of the process is small. Three failure mechanisms are suspected, namely thermo...

Research paper thumbnail of Impact of low PRF tritium permeation barriers-on the water cooled lead lithium blanket: A safety analysis

IEEE/NPSS Symposium on Fusion Engineering, 2002

A summary is here presented concerning the first results in evaluating the safety features of the... more A summary is here presented concerning the first results in evaluating the safety features of the European water-cooled lead lithium blanket in which tritium permeation barriers on the external surface of the breeder cooling pipes are not used or, if used, a lower efficiency is required for them. As a consequence, in this design concept, a significant amount of tritium

Research paper thumbnail of JRC-IE's Research on safety of Gen IV systems

The Institute for Energy (IE), one of the seven scientific Institutes of the Joint Research Centr... more The Institute for Energy (IE), one of the seven scientific Institutes of the Joint Research Centre (JRC) of the European Commission, has the mission to provide scientific and technical support for the conception, development, implementation and monitoring of community policies related to energy. To accomplish its mission, IE performs research in the areas of renewable energies, safety and sustainability of nuclear energy for current & future reactor systems, energy techno/economic assessment, and security of energy supply. The Generation IV International Forum (GIF) is a cooperative international endeavour organized to carry out R&D needed to establish the feasibility and performance capabilities of the next generation nuclear energy systems and support the progress towards their realization. The EU, represented by EURATOM and with the JRC as implementing agent, is working together with other GIF partners to perform pre-competitive R&D on key technologies to be implemented in future...

Research paper thumbnail of EU water-cooled Pb-17Li DEMO blanket: fabrication issues and future R&D priorities

Fusion Science and Technology

EU water-cooled Pb-17Li DEMO blanket: fabrication issues and future R&D priorities

Research paper thumbnail of RAPHAEL: The European Union's (Very) High Temperature Reactor Technology Project

Since the late 1990, the European Union (EU) was conducting work on High Temperature Reactors (HT... more Since the late 1990, the European Union (EU) was conducting work on High Temperature Reactors (HTR) confirming their high potential in terms of safety (inherent safety features), environmental impact (robust fuel with no significant radioactive release), sustainability (high efficiency, potential suitability for various fuel cycles), and economics (simplifications arising from safety features). In April 2005, the EU Commission has started

Research paper thumbnail of Raphael, a European Project for the Development of HTR/VHTR Technology for Industrial Process Heat Supply and Cogeneration

Since the late 1990s, the European Commission is supporting the HTR-TN partnership work on the de... more Since the late 1990s, the European Commission is supporting the HTR-TN partnership work on the development of HTR, that resulted in confirming HTR high potential in terms of safety (inherent safety features), environmental impact (robust fuel without significant radioactive release), sustainability (potential suitability for various fuel cycles), and economics (high efficiency, simplifications arising from safety features). In April 2005, a

Research paper thumbnail of High-Temperature Reactor Fuel Technology in the RAPHAEL European Project

Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 1, 2008

Research paper thumbnail of High-Temperature Reactor Fuel Technology in the European Projects HTR-F1 and Raphael

Research paper thumbnail of JRC's on-line fission gas release monitoring system in the high flux reactor Petten

Nuclear Engineering and Design, 2012

Research paper thumbnail of European energy policy and the potential impact of HTR and nuclear cogeneration

Nuclear Engineering and Design, 2014

Research paper thumbnail of Long term out-of-pile thermocouple tests in conditions representative for nuclear gas-cooled high temperature reactors

Nuclear Engineering and Design, 2014

Research paper thumbnail of Special edition on HTR 2012 conference

Nuclear Engineering and Design, 2014

Research paper thumbnail of LIBRETTO-3: Performance of tritium permeation barriers under irradiation at the HFR Petten

Journal of Nuclear Materials, 1994

Research paper thumbnail of Water-cooled Pb–17Li test blanket module for ITER: Impact of the structural material grade on the neutronic responses

Journal of Nuclear Materials, 1998

Research paper thumbnail of On the use of tin–lithium alloys as breeder material for blankets of fusion power plants

Journal of Nuclear Materials, 2000

Research paper thumbnail of In-pile tritium-permeation measurements on T91 tubes with double walls or a Fe–Al/Al2O3 coating

Journal of Nuclear Materials, 2000