Craig Hamlyn-Harris | Loughborough University (original) (raw)

Papers by Craig Hamlyn-Harris

Research paper thumbnail of Fabrication of full-size mock-up for 10° section of ITER vacuum vessel thermal shield

Fusion Engineering and Design, 2015

Research paper thumbnail of Piping structural design for the ITER thermal shield manifold

Fusion Engineering and Design, 2015

Research paper thumbnail of Structural Analysis of the ITER Thermal Shield for Final Design Verification

IEEE Transactions on Plasma Science, 2014

ABSTRACT The structural rigidity of the ITER Thermal Shield (TS) has been verified by structural ... more ABSTRACT The structural rigidity of the ITER Thermal Shield (TS) has been verified by structural analysis. In this paper, the analysis process, methodology and demonstration of the structural integrity for the TS are described. The analysis are performed for the TS global model and detailed model such as supports and joints. TS joints in the shell model are modeled using orthogonal material properties, because using sufficiently refined joint models in the global model of TS sector is almost impossible and highly time-consuming. Joint orthogonal properties are calculated based on the periodical composite cell theory. To verify the structural rigidity for the TS, plastic collapse, buckling, ratcheting and fatigue are assessed in accordance with ASME VIII, Div. 2.

Research paper thumbnail of In-service inspection and instrumentation for ITER vacuum vessel

ABSTRACT In-service inspection (ISI) is required according to the French Order for Nuclear Pressu... more ABSTRACT In-service inspection (ISI) is required according to the French Order for Nuclear Pressure Equipment and also to protect plant investment and to ensure machine availability. The ITER VV maintenance and monitoring program includes Inservice Monitoring, Periodic Test and Periodic Inspection. Inservice Monitoring includes commissioning tests, continuous vacuum and water leakage monitoring and load follow-on monitoring. Periodic Test includes regular pressure tests and leak tests. For the outer shell welds of the main vessel, the equatorial region of “port #7” and lower penetrations are selected for Periodic Inspection. R&D for ISI is underway and tools and maintenance systems are being developed. Mock-ups were constructed to demonstrate its feasibility. In addition, a study of acoustic emission monitoring has started using a mock-up. The VV instrumentation is a system to monitor the VV status in normal and off-normal conditions. The VV instrumentation system includes approximately 1600 sensors, mounting devices, cables, cable holders, vacuum feed-throughs for the vessel and the cryostat, control cubicles and interrogating systems. Approximately 850 thermocouples are installed to monitor temperatures on plasma-side and cryostat-side surfaces of the vessel. Resistive and FBG strain gauges are also mounted on the vessel surfaces. Displacement sensors and accelerometers are installed to obtain data of VV movements during plasma disruptions or VDEs. These data are utilized to calculate forces on the VV. This calculation is essential to categorize plasma disruption or VDE events during the ITER operational phase.

Research paper thumbnail of Simulation of Electromagnetic Transients in ITER Thermal Shield Manifolds

IEEE Transactions on Applied Superconductivity, 2000

ABSTRACT A study of eddy currents and forces associated with electromagnetic (EM) transients for ... more ABSTRACT A study of eddy currents and forces associated with electromagnetic (EM) transients for the event of current quench in the ITER thermal shield manifolds is presented. EM response of the tokamak passive structures with respect to their inductive coupling has been estimated using the shell approximation. The external field obtained within the model, assuming their 40-degree symmetry, has been applied to the local model of the thermal shield (TS) manifolds covering the 360-degree domain. Fields sources are modeled accurately to the input data description. At this stage of the study related to first estimates of EM loads, acting on the TS manifolds, the electric contact between the cooling tubes and adjacent TS plates was neglected. The current flow is restricted between the neighboring panels. Such simplification uncouples galvanically the manifold tubes from other TS conducting shells, which makes possible a local simulation of eddy currents and EM loads on the manifolds. Two design options with/without electrical breaks in outlet manifolds have been considered. Detailed temporal and spatial distributions of eddy currents and EM forces were obtained. The simulated results were validated in a comparison with a lumped equivalent circuit. Maximal EM loads per unit length were evaluated and found to be low.

Research paper thumbnail of Thermal analysis on detailed 3D models of ITER thermal shield

Fusion Engineering and Design, 2014

ABSTRACT Thermal shield (TS) is to be installed in ITER tokamak to minimize radiation heat load t... more ABSTRACT Thermal shield (TS) is to be installed in ITER tokamak to minimize radiation heat load transferring from the vacuum vessel and the cryostat to the superconducting magnet operating at 4.5 K. The TS shall be properly designed so that the radiation heat load is below the specified requirement for the magnet. This paper describes how the ITER TS is modeled to verify its thermal performance. The 3D finite element (FE) models of repetitive sections of the whole TS were developed in this study. The major geometric simplifications applied to the FE models are illustrated. Passively cooled removable panel on the cryostat TS (CTS) for the in-cryostat maintenance of the magnet was modeled considering thermal contact at the joint. The boundary temperature of the CTS support was determined from the analysis of cryostat with the TS. Total heat load from the TS to the magnet was evaluated for the steady state of plasma operation. Cool-down behavior of the TS was also investigated by the transient analysis of the representative models. The maximum panel temperature and the helium outlet temperature were obtained during cool-down of TS.

Research paper thumbnail of Design finalization and start of construction of ITER vacuum vessel

Fusion Engineering and Design, 2011

The vacuum vessel (VV) design is being finalized including interface components, such as the supp... more The vacuum vessel (VV) design is being finalized including interface components, such as the support rails and feedthroughs of coils for mitigation of edge localized modes (ELM) and vertical stabilization (VS) of the plasma (ELM/VS coils). It was necessary to make adjustments in the locations of the blanket supports and manifolds to accommodate the design modifications in the ELM/VS coils. The lower port gussets were reinforced to keep a sufficient margin under the increased VV load conditions. The VV support design is being finalized as well, with an emphasis on structure simplification. The design of the inwall shielding (IWS) has progressed, considering assembly and required tolerances. The layout of ferritic steel plates and borated steel plates will be optimized based on on-going toroidal field ripple analysis. The VV instrumentation was defined in detail. Strain gauges, thermocouples, displacement meters and accelerometers shall be installed to monitor the status of the VV in normal and off-normal conditions to confirm all safety functions are performed correctly. The ITER VV design was preliminarily approved, and the VV materials including 316L(N) IG were already qualified by the Agreed Notified Body (ANB) according to the procedure of Nuclear Pressure Equipment Order.

Research paper thumbnail of ITER Vacuum Vessel design and construction

Fusion Engineering and Design, 2012

... a , 1 , Corresponding Author Contact Information , E-mail The Corresponding Author , V. Barab... more ... a , 1 , Corresponding Author Contact Information , E-mail The Corresponding Author , V. Barabash a , 1 , C. Bachmann a , 1 , P. Chappuis a , 1 , CH Choi a ... of design option 2.2.2. Design of ELM/VS coils and interfaces with the VV 2.2.3. Reinforcements of lower port gusset 2.2.4 ...

Research paper thumbnail of Final design of ITER vacuum vessel thermal shield

Fusion Engineering and Design, 2013

ABSTRACT The final design of ITER vacuum vessel thermal shield (VVTS), which is planned to be pro... more ABSTRACT The final design of ITER vacuum vessel thermal shield (VVTS), which is planned to be procured completely by Korea, has been implemented after the procurement arrangement was signed. In this paper, the design and the supporting analysis are described for the key components of the VVTS such as joint, panel, support, and stopper. The VVTS design is revised and finalized based on the manufacturing feasibility, interface requirement and assemble feasibility. The inboard and the outboard supports of VVTS are designed in detail considering structural rigidity and assemble feasibility. The shape of in-pit joint, which is installed every 40 degree sector in toroidal direction for compensation of possible misalignment during sector assembly, is determined. Three types of joints are developed in accordance with their locations and assemble feasibilities are checked through the R&D. Stopper design is developed in order to prevent direct contact against adjacent components such as vacuum vessel and magnets. Structural rigidity of the whole VVTS is also validated by finite element analysis under various kinds of operating conditions, such as deadweight, electro-magnetic load, seismic load and load combinations.

Research paper thumbnail of ITER thermal shields at the starting phase of procurement

Fusion Engineering and Design, 2011

Recent progress of the ITER thermal shields (TS) design is presented. As the ITER construction ph... more Recent progress of the ITER thermal shields (TS) design is presented. As the ITER construction phase approaches, the design of the TS has been improved and developed in more detail with the focus on better performance, improved manufacture ability and successful assembly at the ITER-site. Aiming at the supply of the TS components to the ITER-site, the Procurement Arrangement with the Korean Domestic Agency (KO DA) was signed. In cooperation with the Korean industry, a preliminary study of the TS manufacture was performed -accompanied with several R&D activities (including manufacture of a full-size mock-up of the TS panel). Results of all above activities are described in this paper.

Research paper thumbnail of Engineering design of an RF vacuum window for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses ... more The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses titanium alloys for the outer and inner conductors and double conical ceramic insulators. However, unlike the JET window, beryllia is the dielectric material. The design is complicated considerably by the need for continuous RF operation, which necessitates active cooling. Residual stress after manufacture has been optimised with particular attention given to subcritical crack growth in the ceramic. In addition, finite element methods were used to model the steady state temperature gradient from the combined effects of volumetric heating of neutron irradiation, RF surface heating and dielectric loss heating. A scoping study is included in the modelling methodology of bonded joints and on the hydraulic requirements of the window cooling system.

Research paper thumbnail of Mechanical design features and challenges for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 M... more The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 MW. Operation in the ITER environment imposes significant thermal power handling capability, structural integrity, shielding and operations requirements. The design will require a step change over any predecessor in terms of power, scale and complexity. This paper reports the main mechanical design features that address the challenges and often conflicting requirements during the conceptual design phase.

Research paper thumbnail of Engineering design of an RF vacuum window for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses ... more The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses titanium alloys for the outer and inner conductors and double conical ceramic insulators. However, unlike the JET window, beryllia is the dielectric material. The design is complicated considerably by the need for continuous RF operation, which necessitates active cooling. Residual stress after manufacture has been optimised with particular attention given to subcritical crack growth in the ceramic. In addition, finite element methods were used to model the steady state temperature gradient from the combined effects of volumetric heating of neutron irradiation, RF surface heating and dielectric loss heating. A scoping study is included in the modelling methodology of bonded joints and on the hydraulic requirements of the window cooling system.

Research paper thumbnail of Mechanical design features and challenges for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 M... more The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 MW. Operation in the ITER environment imposes significant thermal power handling capability, structural integrity, shielding and operations requirements. The design will require a step change over any predecessor in terms of power, scale and complexity. This paper reports the main mechanical design features that address the challenges and often conflicting requirements during the conceptual design phase.

Research paper thumbnail of Engineering design of an RF vacuum window for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses ... more The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses titanium alloys for the outer and inner conductors and double conical ceramic insulators. However, unlike the JET window, beryllia is the dielectric material. The design is complicated considerably by the need for continuous RF operation, which necessitates active cooling. Residual stress after manufacture has been optimised with particular attention given to subcritical crack growth in the ceramic. In addition, finite element methods were used to model the steady state temperature gradient from the combined effects of volumetric heating of neutron irradiation, RF surface heating and dielectric loss heating. A scoping study is included in the modelling methodology of bonded joints and on the hydraulic requirements of the window cooling system.

Research paper thumbnail of Mechanical design features and challenges for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 M... more The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 MW. Operation in the ITER environment imposes significant thermal power handling capability, structural integrity, shielding and operations requirements. The design will require a step change over any predecessor in terms of power, scale and complexity. This paper reports the main mechanical design features that address the challenges and often conflicting requirements during the conceptual design phase.

Research paper thumbnail of Fabrication of full-size mock-up for 10° section of ITER vacuum vessel thermal shield

Fusion Engineering and Design, 2015

Research paper thumbnail of Piping structural design for the ITER thermal shield manifold

Fusion Engineering and Design, 2015

Research paper thumbnail of Structural Analysis of the ITER Thermal Shield for Final Design Verification

IEEE Transactions on Plasma Science, 2014

ABSTRACT The structural rigidity of the ITER Thermal Shield (TS) has been verified by structural ... more ABSTRACT The structural rigidity of the ITER Thermal Shield (TS) has been verified by structural analysis. In this paper, the analysis process, methodology and demonstration of the structural integrity for the TS are described. The analysis are performed for the TS global model and detailed model such as supports and joints. TS joints in the shell model are modeled using orthogonal material properties, because using sufficiently refined joint models in the global model of TS sector is almost impossible and highly time-consuming. Joint orthogonal properties are calculated based on the periodical composite cell theory. To verify the structural rigidity for the TS, plastic collapse, buckling, ratcheting and fatigue are assessed in accordance with ASME VIII, Div. 2.

Research paper thumbnail of In-service inspection and instrumentation for ITER vacuum vessel

ABSTRACT In-service inspection (ISI) is required according to the French Order for Nuclear Pressu... more ABSTRACT In-service inspection (ISI) is required according to the French Order for Nuclear Pressure Equipment and also to protect plant investment and to ensure machine availability. The ITER VV maintenance and monitoring program includes Inservice Monitoring, Periodic Test and Periodic Inspection. Inservice Monitoring includes commissioning tests, continuous vacuum and water leakage monitoring and load follow-on monitoring. Periodic Test includes regular pressure tests and leak tests. For the outer shell welds of the main vessel, the equatorial region of “port #7” and lower penetrations are selected for Periodic Inspection. R&D for ISI is underway and tools and maintenance systems are being developed. Mock-ups were constructed to demonstrate its feasibility. In addition, a study of acoustic emission monitoring has started using a mock-up. The VV instrumentation is a system to monitor the VV status in normal and off-normal conditions. The VV instrumentation system includes approximately 1600 sensors, mounting devices, cables, cable holders, vacuum feed-throughs for the vessel and the cryostat, control cubicles and interrogating systems. Approximately 850 thermocouples are installed to monitor temperatures on plasma-side and cryostat-side surfaces of the vessel. Resistive and FBG strain gauges are also mounted on the vessel surfaces. Displacement sensors and accelerometers are installed to obtain data of VV movements during plasma disruptions or VDEs. These data are utilized to calculate forces on the VV. This calculation is essential to categorize plasma disruption or VDE events during the ITER operational phase.

Research paper thumbnail of Simulation of Electromagnetic Transients in ITER Thermal Shield Manifolds

IEEE Transactions on Applied Superconductivity, 2000

ABSTRACT A study of eddy currents and forces associated with electromagnetic (EM) transients for ... more ABSTRACT A study of eddy currents and forces associated with electromagnetic (EM) transients for the event of current quench in the ITER thermal shield manifolds is presented. EM response of the tokamak passive structures with respect to their inductive coupling has been estimated using the shell approximation. The external field obtained within the model, assuming their 40-degree symmetry, has been applied to the local model of the thermal shield (TS) manifolds covering the 360-degree domain. Fields sources are modeled accurately to the input data description. At this stage of the study related to first estimates of EM loads, acting on the TS manifolds, the electric contact between the cooling tubes and adjacent TS plates was neglected. The current flow is restricted between the neighboring panels. Such simplification uncouples galvanically the manifold tubes from other TS conducting shells, which makes possible a local simulation of eddy currents and EM loads on the manifolds. Two design options with/without electrical breaks in outlet manifolds have been considered. Detailed temporal and spatial distributions of eddy currents and EM forces were obtained. The simulated results were validated in a comparison with a lumped equivalent circuit. Maximal EM loads per unit length were evaluated and found to be low.

Research paper thumbnail of Thermal analysis on detailed 3D models of ITER thermal shield

Fusion Engineering and Design, 2014

ABSTRACT Thermal shield (TS) is to be installed in ITER tokamak to minimize radiation heat load t... more ABSTRACT Thermal shield (TS) is to be installed in ITER tokamak to minimize radiation heat load transferring from the vacuum vessel and the cryostat to the superconducting magnet operating at 4.5 K. The TS shall be properly designed so that the radiation heat load is below the specified requirement for the magnet. This paper describes how the ITER TS is modeled to verify its thermal performance. The 3D finite element (FE) models of repetitive sections of the whole TS were developed in this study. The major geometric simplifications applied to the FE models are illustrated. Passively cooled removable panel on the cryostat TS (CTS) for the in-cryostat maintenance of the magnet was modeled considering thermal contact at the joint. The boundary temperature of the CTS support was determined from the analysis of cryostat with the TS. Total heat load from the TS to the magnet was evaluated for the steady state of plasma operation. Cool-down behavior of the TS was also investigated by the transient analysis of the representative models. The maximum panel temperature and the helium outlet temperature were obtained during cool-down of TS.

Research paper thumbnail of Design finalization and start of construction of ITER vacuum vessel

Fusion Engineering and Design, 2011

The vacuum vessel (VV) design is being finalized including interface components, such as the supp... more The vacuum vessel (VV) design is being finalized including interface components, such as the support rails and feedthroughs of coils for mitigation of edge localized modes (ELM) and vertical stabilization (VS) of the plasma (ELM/VS coils). It was necessary to make adjustments in the locations of the blanket supports and manifolds to accommodate the design modifications in the ELM/VS coils. The lower port gussets were reinforced to keep a sufficient margin under the increased VV load conditions. The VV support design is being finalized as well, with an emphasis on structure simplification. The design of the inwall shielding (IWS) has progressed, considering assembly and required tolerances. The layout of ferritic steel plates and borated steel plates will be optimized based on on-going toroidal field ripple analysis. The VV instrumentation was defined in detail. Strain gauges, thermocouples, displacement meters and accelerometers shall be installed to monitor the status of the VV in normal and off-normal conditions to confirm all safety functions are performed correctly. The ITER VV design was preliminarily approved, and the VV materials including 316L(N) IG were already qualified by the Agreed Notified Body (ANB) according to the procedure of Nuclear Pressure Equipment Order.

Research paper thumbnail of ITER Vacuum Vessel design and construction

Fusion Engineering and Design, 2012

... a , 1 , Corresponding Author Contact Information , E-mail The Corresponding Author , V. Barab... more ... a , 1 , Corresponding Author Contact Information , E-mail The Corresponding Author , V. Barabash a , 1 , C. Bachmann a , 1 , P. Chappuis a , 1 , CH Choi a ... of design option 2.2.2. Design of ELM/VS coils and interfaces with the VV 2.2.3. Reinforcements of lower port gusset 2.2.4 ...

Research paper thumbnail of Final design of ITER vacuum vessel thermal shield

Fusion Engineering and Design, 2013

ABSTRACT The final design of ITER vacuum vessel thermal shield (VVTS), which is planned to be pro... more ABSTRACT The final design of ITER vacuum vessel thermal shield (VVTS), which is planned to be procured completely by Korea, has been implemented after the procurement arrangement was signed. In this paper, the design and the supporting analysis are described for the key components of the VVTS such as joint, panel, support, and stopper. The VVTS design is revised and finalized based on the manufacturing feasibility, interface requirement and assemble feasibility. The inboard and the outboard supports of VVTS are designed in detail considering structural rigidity and assemble feasibility. The shape of in-pit joint, which is installed every 40 degree sector in toroidal direction for compensation of possible misalignment during sector assembly, is determined. Three types of joints are developed in accordance with their locations and assemble feasibilities are checked through the R&D. Stopper design is developed in order to prevent direct contact against adjacent components such as vacuum vessel and magnets. Structural rigidity of the whole VVTS is also validated by finite element analysis under various kinds of operating conditions, such as deadweight, electro-magnetic load, seismic load and load combinations.

Research paper thumbnail of ITER thermal shields at the starting phase of procurement

Fusion Engineering and Design, 2011

Recent progress of the ITER thermal shields (TS) design is presented. As the ITER construction ph... more Recent progress of the ITER thermal shields (TS) design is presented. As the ITER construction phase approaches, the design of the TS has been improved and developed in more detail with the focus on better performance, improved manufacture ability and successful assembly at the ITER-site. Aiming at the supply of the TS components to the ITER-site, the Procurement Arrangement with the Korean Domestic Agency (KO DA) was signed. In cooperation with the Korean industry, a preliminary study of the TS manufacture was performed -accompanied with several R&D activities (including manufacture of a full-size mock-up of the TS panel). Results of all above activities are described in this paper.

Research paper thumbnail of Engineering design of an RF vacuum window for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses ... more The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses titanium alloys for the outer and inner conductors and double conical ceramic insulators. However, unlike the JET window, beryllia is the dielectric material. The design is complicated considerably by the need for continuous RF operation, which necessitates active cooling. Residual stress after manufacture has been optimised with particular attention given to subcritical crack growth in the ceramic. In addition, finite element methods were used to model the steady state temperature gradient from the combined effects of volumetric heating of neutron irradiation, RF surface heating and dielectric loss heating. A scoping study is included in the modelling methodology of bonded joints and on the hydraulic requirements of the window cooling system.

Research paper thumbnail of Mechanical design features and challenges for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 M... more The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 MW. Operation in the ITER environment imposes significant thermal power handling capability, structural integrity, shielding and operations requirements. The design will require a step change over any predecessor in terms of power, scale and complexity. This paper reports the main mechanical design features that address the challenges and often conflicting requirements during the conceptual design phase.

Research paper thumbnail of Engineering design of an RF vacuum window for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses ... more The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses titanium alloys for the outer and inner conductors and double conical ceramic insulators. However, unlike the JET window, beryllia is the dielectric material. The design is complicated considerably by the need for continuous RF operation, which necessitates active cooling. Residual stress after manufacture has been optimised with particular attention given to subcritical crack growth in the ceramic. In addition, finite element methods were used to model the steady state temperature gradient from the combined effects of volumetric heating of neutron irradiation, RF surface heating and dielectric loss heating. A scoping study is included in the modelling methodology of bonded joints and on the hydraulic requirements of the window cooling system.

Research paper thumbnail of Mechanical design features and challenges for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 M... more The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 MW. Operation in the ITER environment imposes significant thermal power handling capability, structural integrity, shielding and operations requirements. The design will require a step change over any predecessor in terms of power, scale and complexity. This paper reports the main mechanical design features that address the challenges and often conflicting requirements during the conceptual design phase.

Research paper thumbnail of Engineering design of an RF vacuum window for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses ... more The RF vacuum window design proposed for ITER is similar to the one in operation on JET. It uses titanium alloys for the outer and inner conductors and double conical ceramic insulators. However, unlike the JET window, beryllia is the dielectric material. The design is complicated considerably by the need for continuous RF operation, which necessitates active cooling. Residual stress after manufacture has been optimised with particular attention given to subcritical crack growth in the ceramic. In addition, finite element methods were used to model the steady state temperature gradient from the combined effects of volumetric heating of neutron irradiation, RF surface heating and dielectric loss heating. A scoping study is included in the modelling methodology of bonded joints and on the hydraulic requirements of the window cooling system.

Research paper thumbnail of Mechanical design features and challenges for the ITER ICRH antenna

Fusion Engineering and Design, 2009

The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 M... more The ITER Ion Cyclotron Resonant Heating (ICRH) antenna provides plasma heating at a power of 20 MW. Operation in the ITER environment imposes significant thermal power handling capability, structural integrity, shielding and operations requirements. The design will require a step change over any predecessor in terms of power, scale and complexity. This paper reports the main mechanical design features that address the challenges and often conflicting requirements during the conceptual design phase.