ITER vacuum vessel structural analysis completion during manufacturing phase

Martinez, Jean-Marc; Alekseev, A.; Sborchia, C.; Choi, Changhwan; Utin, Y.; Jun, Chang; Terasawa, A.; Popova, E.; Xiang, Bin; Sannazaro, G.; Lee, A.; Martín, A.; Teissier, P.; Sabourin, Flavien; Caixas, Joan; Fernández, Elena Cuasante; Zarzalejos, José María; Kim, Heung-Su; Kim, Y.G.; Privalova, E.; Du, Sheng; Wang, Shiwei; Albin, V.; Gaucher, T.; Borrelly, S.; Cambazar, M.; Sfarni, Samir

doi:10.1016/j.fusengdes.2016.02.017

Cited by 7 publications

(7 citation statements)

References 7 publications

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“…As-built design of the ITER VV has to maintain the required structural margin from the RCC-MR code and French regulation under possible all loading conditions during the ITER operation such as pressure loads by the cooling water and vacuum conditions, electromagnetic loads by the magnetic field interaction between operating plasma and magnets, seismic loads by hypothetical earthquake event, and thermal loads by temperature gradients caused by neutron heating and water cooling in addition to the dead weight of the system [20]. Various structural verifications have been performed using global and local analysis models to confirm the structural integrity under the critical load cases for the design modification proposals to satisfy the manufacturing requirement and non-conformances: application scallop design for the ribs to avoid cross welding, reduction of the welding length of the rib, misalignment and local volumetric examination limitation on the assembled joint.…”

Section: Other Challengesmentioning

confidence: 99%

Manufacturing completion of the first ITER vacuum vessel sector

et al. 2022

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In April 2020, manufacturing of the ITER vacuum vessel (VV) 1st sector has been completed by Korea domestic agency (KODA) since manufacturing started in February 2012. The ITER VV sector is the largest fusion VV structure in the world. Each step of the manufacturing was challenged as a first-of-a-kind (FOAK), and a French nuclear pressure vessel. The paper provides an overview of the major challenges which were overcome over the last 10 years.

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Section: Other Challengesmentioning

confidence: 99%

Manufacturing completion of the first ITER vacuum vessel sector

et al. 2022

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“…In addition, the Vacuum Vessel is classified as safety class-1 component according to the ITER classification: this is the primary confinement barrier of the ITER nuclear installation. In order to get licencing of this pressure equipment system by the French regulator (ASN), it has been decided to implement the RCC-MR [3] as the reference design and construction code [4]. This nuclear code provides detailed and basic rules for the design, manufacturing, installation, commissioning and in-service inspection of nuclear plant devices.…”

Section: The Iter First Confinement Barriermentioning

confidence: 99%

“…29 shows the manifold rails of the blanket system in the ITER vacuum vessel. The design justification for these rails consists in evaluating the maximum stress and/or strain in the weld cross section for the worst load combination [4], and comparing it with design criteria defined in the RCC-MR code.…”

Section: Application To Iter Vacuum Vessel (Vv) Support Railmentioning

confidence: 99%

“…Because of the large amount of rails in the VV and all the different mechanical load types that could act on it, the method proposed here consists in redefining the loading vector applied at the centroid of the weld cross section A (in m 2 ) in two forces: one normal force Fn(t) (in N) and one tangential force Ft(t) (in N), see eq. ( 87)-( 88 where Fx, Fy, Fz are the forces, and Mx, My, Mz are the moments (in N.m) defined in a given orthonormal basis (x, y, z), and e corresponds to the rail thickness (in m), w the rail width (in m), Ix and Iy are the flexion moments of inertia (in m 4 ). The force induced by torsion in a rectangular section, Ftorque (N), has been adapted from [31].…”

Section: Thermomechanical Test Hypothesismentioning

confidence: 99%

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Development of a thermo-mechanical behaviour model adapted to the ITER vacuum vessel material

Sabourin

Désoyer

Lejeunes

et al. 2021

Fusion Engineering and Design

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The ITER machine has been classified as a Basic Nuclear Installation French nuclear regulator (INB n°174), which implies that it will be the first fusion reactor to go through complete French nuclear licencing. The combination of mechanic and electromagnetic phenomena with the heat loads caused by neutron streaming requires a multi-physics approach to the damage assessment, which has not yet been implemented in the common nuclear codes and standards.The general damage prevention methodology consists in guaranteeing the structural integrity of a component. The development of design rules has mainly two origins: prevention of damage from monotonic mechanical loads and prevention of damage from repeated application of loads. In most cases, structural integrity is justified within a linear elastic behaviour but when this route is not enough to respect the design criteria, several non-linear approaches to the material's mechanical behaviour can be considered, requiring more elaborated demonstration of the design compliance. Nevertheless, the models proposed in the nuclear model database are sometimes not sufficient to properly describe the experimentally observed cyclic plasticity behaviour and, in particular, the ratcheting and shakedown phenomena.According to ITER community experts in materials and analyses, a thermo-mechanical behaviour model fitting the ITER Tokamak materials data will guarantee the best prediction of the damage considering a nuclear and a multi-physic loading condition.This paper describes the assessment of the non-linear behaviour of Vacuum Vessel (VV) material with a strong thermomechanical coupling and a damage parameter to prevent crack initiation. More precisely, Chaboche's models available in the literature (elasto-(visco)-plasticity models, with various types of hardening) have been enriched in order to explicitly take into account the influence of the temperature on the mechanical behaviour and, reciprocally, the influence of the mechanical behaviour on the temperature. Mechanical cycling tests have been performed on the VV constitutive material, emphasizing on the progressive deformation state up to failure mode, i.e., ratcheting. The proposed models have been tested on a homogeneous problem and the results compared with uniaxial test results; this type of simulation is commonly called "0D"analysis. The last part of this document describes the finite element implementation of the constitutive material model and its application to the ITER VV welded support.

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“…The ITER vacuum vessel (Martinez et al, 2016), consisting of the main vessel, port structures and supporting system, provides a hermetically sealed plasma container which also fulfils the critical role of first tritium containment barrier. It is a water-cooled austenitic stainless steel (SS 316L(N)) pressure vessel with an outer diameter of 19.4 m, a height of 11.4 m and an inner volume of 1400 m 3 .…”

Section: Tokamak Core Systemsmentioning

confidence: 99%