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Assessment of a bolted-flange connection for ITER test blanket module

FUSION ENGINEERING AND DESIGN 2021年 165卷 112247-112247页

作者： Zaouter, T. Vulliez, K. Michel, B. Gazzotti, S. Friconneau, J-P Martins, J-P Univ Montpellier Lab Etancheite DE2D SEADISECCEADES Marcoule France CEA Cadarache IRFM F-13108 St Paul Les Durance France ITER Org Route Vinon Sur Verdon F-13067 St Paul Les Durance France

In ITER, the 'Pipe Forest (PF)' is a network of pipes that connects the Ancillary Equipment Unit to the test blanket module (TBM) at the level of the equatorial port-plug of the reactor prototype. The goal of ITER's TBM program is to validate concepts to be adopted for the DEMO tritium Breeding blankets. Different types of pipes are mounted on the port-plug among which those used for cooling or tritium processing. During plasma operation, the PF has to accommodate severe thermomechanical loads. It shall also provide protection from abnormal contamination and be designed to ease connection/disconnection operations. With numerical simulation, this work assesses the use of bolted flanges as an alternative to the welded solution to connect the PF on the TBMs inside the port cell environment. The proposed designs integrate metallic seals as well as an embedded cooling system in the flanges when necessary, to limit the temperature of the seals and the bolts and prevent irreversible damage. It is shown that bolted-flange junctions for the PF are a credible solution. Still, important stresses in the socket of the flanges are present but do not represent a problematic issue for dimensioning purposes, as they shall be accommodated with a small amount of plastic strain.

关键词： Bolted-flange Numerical simulation ITER test blanket module Pipe Forest

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Evaluation of conservative and innovative manufacturing routes for gas cooled test blanket module and Breeding blanket First Walls

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FUSION ENGINEERING AND DESIGN 2019年第PartB期146卷 2140-2143页

作者： Neuberger, Heiko Rey, Joerg Arbeiter, Frederik Hernandez, Francisco Ruck, Sebastian Koehly, Christina Stratil, Ludek Niewoehner, Reinhard Felde, Alexander Karlsruhe Inst Technol Karlsruhe Germany Inst Phys Mat ASCR Brno Czech Republic FGU Stuttgart Germany Inst Umformtech IFU Stuttgart Germany

Different manufacturing routes are investigated at the KIT INR for the realization of First Walls (FW) for nuclear fusion components, such as the ITER test blanket module (TBM) and DEMO Breeding blankets (BB) for the Helium Cooled Pebble Bed (HCPB) Breeding concept. One conventional manufacturing route mainly basing of Electrical Discharge Machining (EDM) and forming was demonstrated successfully. However, the procurement costs are high. Therefore, options also to apply Additive Manufacturing (AM) as alternative were investigated. This paper compares the HCPB reference concept for FW fabrication to innovative concepts basing on AM.

关键词： First wall Breeding blanket test blanket module Manufacturing Additive Manufacturing

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Analysis of test blanket module attachments under electromagnetic loads by using a dynamic amplification factor envelope

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FUSION ENGINEERING AND DESIGN 2018年第PartB期136卷 1247-1251页

作者： Munoz, Raud Calvo, Francisco J. Sadaba, Sergio Gil, Ana M. Rodriguez, Javier Vallory, Joelle Zmitko, Milan Poitevin, Yves IDOM Avda Monasterio El Escorial4 Madrid 28049 Spain Fus Energy F4E Torres Diagonal Litoral B3C Josep Pla 2 Barcelona 08019 Spain

European test blanket modules (TBMs) are attached to radiation shields through mechanical joints. The structural integrity of the joints must be ensured under non-periodic dynamic loading caused by accidental electromagnetic events. This requires the transient dynamic analysis of the TBM-Joint-Shield under multiple loading scenarios. As temperatures and dynamic characteristics of the TBM-Joint-Shield system are updated under the course of the ITER project, the design process of the joints can become very time-consuming. This work presents a methodology based on a response spectrum to simplify the design process of the joint under electromagnetic loads. The mechanical system TBM-Joint-Shield was modeled as a single degree of freedom lumped spring-mass-dashpot system. The dynamic amplification was determined for a wide range of frequencies using the Finite Element Method. Eventually, a design envelope for each loading category was obtained, which can be readily used for determining the dynamic amplification factor of any potential new design of the TBM + Joint + Shield system. Results showed that helium cooled lithium lead (HCLL) undergoes higher loads than helium cooled pebble bed (HCPB), resulting in a dynamic amplification factor which varies from 1.25 to 2.0 for a damping of 4%.

关键词： test blanket module Electromagnetic loads Finite element analysis Response spectrum

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Experimental investigations of flow distribution in coolant system of Helium-Cooled-Pebble-Bed test blanket module

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FUSION ENGINEERING AND DESIGN 2016年 103卷 53-68页

作者： Ilic, M. Schlindwein, G. Meyder, R. Kuhn, T. Albrecht, O. Zinn, K. Karlsruhe Inst Technol Inst Neutron Phys & Reactor Technol D-76021 Karlsruhe Germany

This paper deals with investigations of flow distribution in the coolant system of the Helium-Cooled Pebble -Bed test blanket module (HCPB TBM) for ITER. The investigations have been performed by manufacturing and testing of an experimental facility named GRICAMAN. The facility involves the upper poloidal half of HCPB TBM bounded at outlets of the first wall channels, at outlet of by-pass pipe and at outlets of cooling channels in breeding units. In this way, the focus is placed on the flow distribution in two mid manifolds of the 4-manifold system: (i) manifold 2 to which outlets of the first wall channels and inlet of by-pass pipe are attached and (ii) manifold 3 which supplies channels in breeding units with helium coolant. These two manifolds are connected with cooling channels in vertical/horizontal grids and caps. The experimental facility has been built keeping the internal structure of manifold 2 and manifold 3 exactly as designed in HCPB TBM. The cooling channels in stiffening grids, caps and breeding units are substituted by so-called equivalent channels which provide the same hydraulic resistance and inlet/outlet conditions, but have significantly simpler geometry than the real channels. Using the conditions of flow similarity, the air pressurized at 0.3 MPa and at ambient temperature has been used as working fluid instead of HCPB TBM helium coolant at 8 MPa and an average temperature of 370 degrees C. The flow distribution has been determined by flow rate measurements at each of 28 equivalent channels, while the pressure distribution has been obtained measuring differential pressure at more than 250 positions. The measured data have shown that critical for flow distribution in manifold 2 are grid/cap channels attached to the manifold regions adjacent to the first wall. In these regions high velocity jets exiting from the first wall induce low pressure at the channel inlets and, therefore, lower flow supply. Making resistance to high velocity streams from

关键词： test blanket module Coolant system Experimental facility Flow rate distribution Pressure distribution

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Experimental and numerical investigations of heat transfer in the first wall of Helium-Cooled-Pebble-Bed test blanket module - Part 1: Presentation of test section and 3D CFD model

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FUSION ENGINEERING AND DESIGN 2015年 90卷 29-36页

作者： Ilic, M. Messemer, G. Zinn, K. Meyder, R. Kecskes, S. Kiss, B. Karlsruhe Inst Technol Inst Neutron Phys & Reactor Technol D-76021 Karlsruhe Germany Budapest Univ Technol & Econ Inst Nucl Tech Budapest Hungary

This paper deals with cooling of the first wall of Helium-Cooled-Pebble-Bed test blanket module (HCPB TBM) for ITER. The first wall cooling is an important investigation issue due to an extreme asymmetry of heat loads: heat flux on the plasma facing side is several times stronger than the one on the side which faces breeding units. Our preliminary 3D CFD analysis revealed that under such conditions the heat transfer coefficient is significantly lower than predicted by common heat transfer correlations (see Ilic et al., 2006). For an experimental validation of these results HETRA (HEat TRAnsfer)test section has been designed and built at the Institute for Neutron Physics and Reactor Technology in Karlsruhe Institute of Technology. The HETRA test section involves in full scale one U-pass of the cooling channel in the first wall of HCPB TBM Version 1.1 (see Meyder et al., 2005). The HCPB TBM relevant experimental conditions have been provided: test channel made of Eurofer steel, helium coolant at pressure of 8 MPa and inlet temperature of 300 C and heat flux of 270 kW/m(2) at the channel surface representing plasma facing side of the first wall. test channels with hydraulically smooth and with hydraulically rough walls have been built. At each test channel the temperature of Eurofer walls has been measured at 60 positions, For numerical investigations the 3D CFD modelling with the code STAR CD has been applied. This paper is the first report on this study and presents the development of the test section and of the 3D CFD model. The analyses of the obtained experimental and computational results are presented in the second report (see Ilic et al., 2014). 2014 Elsevier B.V. All rights reserved.

关键词： test blanket module The first wall Heat transfer test section 3D CFD model

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Construction of a test platform for test blanket module (TBM) systems integration and maintenance in ITER Port Cell #16

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FUSION ENGINEERING AND DESIGN 2015年 96-97卷 365-368页

作者： Vala, Ladislav Reungoat, Mathieu Vician, Martin Poitevin, Yves Ricapito, Italo Zmitko, Milan Panayotov, Dobromir Ctr Vyzkumu Rez Husinec Rez 25068 Czech Republic Fus Energy Barcelona 08019 Spain

This paper describes a project of a non-nuclear, 1:1 scale testing platform dedicated to tests, optimization and validation of integration and maintenance operations for the European TBM systems in the ITER Port Cell #16. This TBM platform is currently under construction in Centrum vyzkumu Rez, Czech Republic. The facility is realized within the scope of the SUSEN project and its full operation is foreseen in the first half of 2016. (C) 2015 Elsevier B.V. All rights reserved.

关键词： test blanket module ITER Maintenance Remote handling

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Construction of a test platform for test blanket module (TBM) systems integration and maintenance in ITER Port Cell #16

Construction of a test platform for Test Blanket Module (TBM...

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28th Symposium on Fusion Technology (SOFT)

关键词： test blanket module ITER Maintenance Remote handling

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ITER fast ion confinement in the presence of the European test blanket module

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NUCLEAR FUSION 2015年第9期55卷 093010-093010页

作者： Akaslompolo, Simppa Kurki-Suonio, Taina Asunta, Otto Cavinato, Mario Gagliardi, Mario Hirvijoki, Eero Saibene, Gabriella Sipila, Seppo Snicker, Antti Sarkimaki, Konsta Varje, Jari Aalto Univ Dept Appl Phys FI-00076 Aalto Finland Torres Diagonal Litoral Fus Energy Barcelona 08019 Spain

This paper addresses the confinement of thermonuclear alpha particles and neutral beam injected deuterons in the 15 MA Q = 10 inductive scenario in the presence of the magnetic perturbation caused by the helium cooled pebble bed test blanket module using the vacuum approximation. Both the flat top phase and plasma ramp-up are studied. The transport of fast ions is calculated using the Monte Carlo guiding center orbit-following code ASCOT. A detailed three-dimensional wall, derived from the ITER blanket module CAD data, is used for evaluating the fast ion wall loads. The effect of the test blanket module is studied for both overall confinement and possible hot spots. The study indicates that the test blanket modules do not significantly deteriorate the fast ion confinement.

关键词： ITER fast ions test blanket module wall loads orbit following Monte Carlo

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Instrumentation integration in the European test blanket modules

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FUSION ENGINEERING AND DESIGN 2024年 202卷

作者： Rodriguez-Lopez, Eduardo Alonso, David Dominguez, Victor Maqueda, Luis Nunez, Celia Rueda, Fernando Vallory, Joelle Forte, Ruggero Fantini, Francesca Ricapito, Italo Poitevin, Yves Esteyco Mech Avda Burgos 12-B Bajo Madrid 28036 Spain Fus Energy Josep Pla 2Torres Diagonal Litoral B3 Barcelona 08019 Spain ATG Sci & Engn Plaza Ernest Lluch i Marti 5 Barcelona 08019 Spain Fus Energy P58 F4E Off 82-P58 F4E OffRoute Vinon Sur Verdon F-13115 Verdon France

Amongst the four different test blanket modules (TBM) that shall be tested in ITER, the European domestic agency (Fusion For Energy) participates in two concepts: the Water-Cooled Lithium Lead (WCLL) and the Helium-Cooled Ceramic Pebbles (HCCP). A progressive set of activities including implementation and integration of instrumentation has been conducted from preliminary design stage. The current work is mainly focused on the thermal and mechanical instrumentation, although other sensors are also considered. The integration of instrumentation in the TBMs is challenging;consequently, the number and position of the sensors should be carefully optimized. An important advance of the current work is the use of reconstruction algorithms to provide an estimation of the reconstruction ability of the different sensor sets. These algorithms comprise a series of mathematical tools which use model results and sensor measurements to infer different variables at positions where no in-situ measurement is available. Apart from the use of these algorithms, the final decision on sensor location has been conducted from a holistic point of view considering the different perspectives and integration challenges.

关键词： Instrumentation integration test blanket module Reconstruction algorithms Sensor optimization

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test blanket modules (ITER) and breeding blanket (DEMO): History of major fabrication technologies development of HCLL and HCPB and status

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FUSION ENGINEERING AND DESIGN 2020年 154卷 111493-111493页

作者： Forest, Laurent Boccaccini, Lorenzo Virgilio Cogneau, Laurence Puma, Antonella Li Neuberger, Heiko Pascal, Serge Rey, Joerg Thomas, Noel Tosi, Jerome Zmitko, Milan Univ Paris Saclay CEA SEMT DEN F-91191 Gif Sur Yvette France KIT Karlsruhe Germany CEA LITEN DRT F-38000 Grenoble France ATMOSTAT F-94815 Villejuif France Fus Energy F4E Josep Pla 2 Barcelona Spain

Two breeding blanket concepts, the Helium-Cooled Lithium-Lead (HCLL) and the Helium-Cooled Pebble-Bed (HCPB), developed in Europe in the frame of DEMO and relevant TBM studies, present many similarities in terms of design and manufacturing. As an example, all structure sub-components are internally cooled by helium circulating in meandering squared section channels. Several technologies have been investigated in the frame of EU fusion research programme for the manufacturing, including a specialized machining, fusion and diffusion welding and joints inspection, of DEMO breeding blanket and TBM sub-components (Cooling Plates (CP), Side Caps (SCs), Stiffening Plates (SPs), First Wall (FW)) and their assembly, main of which are discussed in this paper. The manufacturability of DEMO blanket modules Back Supporting Structure (BSS), a big structure located behind blanket modules and supporting them, is also discussed. The applicability of technologies takes into account specificities of EUROFER97 steel, foreseen as structural material. For each assessed technology, main results, e.g. in terms of mechanical properties and microstructure of weld joints, are presented and main advantages and drawbacks are summed up, in order to identify most promising technology/ies and to propose manufacturing scenarios. It should be noted that these developments are performed according to standards and professional codes (RCC-MRx). Further development strategies are also briefly discussed in the paper.

关键词： test blanket module Breeding blanket EUROFER97 Manufacturing

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