The ITER Equatorial Visible/Infra-Red Wide Angle Viewing System: Status of design and R&amp;D

Salasca, S.; Aumeunier, Marie-Hélène; Benoit, F.; Cantone, B.; Corre, Y.; Delchambre, E.; Ferlet, Marc; Gauthier, E.; Guillon, Christophe; Houtte, D. van; Keller, D.; Labassé, Florence; Larroque, S.; Loarer, T.; Micolon, Frederic; Peluso, Bertrand; Proust, M.; Blanchet, David; Pénéliau, Y.; Alonso, Javier; Cal, E. de la; Hidalgo, C.; Martin, P.; Medrano, M.; Mota, F.; Pablos, J.L. de; Ríos, Luis; Rincón, E.; Vila, R.; Manzanares, A.; Martin, Vincent; Reichle, R.; Guern, F. Le

doi:10.1016/j.fusengdes.2015.02.062

Cited by 25 publications

(5 citation statements)

References 3 publications

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“…In order to evaluate the corresponding effect on DPA rates, the examples of the fuel cladding in the Sodium Fast Reactor (SFR) Phenix and the inner surface of RPV in a French 900 MWe PWR are shown because the DPA of the fuel cladding (RPV) in fast reactors (thermal reactors) is the most important factor concerning the fuel cycle length (operating lifetime) reactors. In addition, the DPA rates in a first mirror unit of the Equatorial Visible Infra-Red Wide Angle Viewing System, which is in the diagnostic first wall of the International Thermonuclear Experimental Reactor (ITER) [30], are investigated to evaluate the influence on fusion reactors.…”

Section: Application In Nuclear Facilitiesmentioning

confidence: 99%

“…The analysis on the role of high-order Legendre polynomials is also carried out for 52 Cr and 58 Ni, which are the most abundant isotopes in nature Cr and Ni, respectively. Figure 19 illustrates the damage cross section of neutron elastic scattering of 58 In addition, the DPA rates in a first mirror unit of the Equatorial Visible Infra-Red Wide Angle Viewing System, which is in the diagnostic first wall of the International Thermonuclear Experimental Reactor (ITER) [30], are investigated to evaluate the influence on fusion reactors.…”

Section: Dpa Cross Sections and Legendre Ordersmentioning

confidence: 99%

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Calculation and verification of neutron irradiation damage with differential cross sections

Chen

Bernard

Tamagno

et al. 2019

Nuclear Instruments and Methods in Physics Research Section B:

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The Displacement per Atom (DPA) rate is conventionally computed with DPA cross sections in reactor applications. The method of direct calculation with energyangular distributions given in the Center of Mass (CM) frame is proposed and recommended in the present work. The methods for refining and verifying the calculations of DPA cross sections are proposed: (i) Gauss-Legendre-Quadrature-based Piecewise Integration (GLQPI) for ensuring the numeric convergence of integral over emission angle due to the discontinuity of integrand; (ii) verification of the convergence for trapezoidal integration over the secondary energy; (iii) interpolation of doubledifferential cross sections. For 56 Fe of JEFF-3.1.1, the current numeric integration over emission angle is shown not convergent, whereas the direct trapezoidal over the secondary energy and the direct interpolation of energy-angle-integrated damage are shown accurate. On the other hand, it is shown that the DPA cross sections are overestimated if isotropic angular distributions are assumed. However, the DPA cross section is not sensitive to the high-order Legendre polynomials because the former is an angle-integrated quantity. Numerical results of neutron elastic scattering show that 2 orders of Legendre polynomials can give the DPA rates of 56 Fe within 0.5% overestimation for fission reactors, while 4 orders are required for fusion reactors. For neutron inelastic scatterings-induced DPA, the first order Legendre polynomial is sufficient for both fission and fusion reactors.

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Section: Application In Nuclear Facilitiesmentioning

confidence: 99%

Section: Dpa Cross Sections and Legendre Ordersmentioning

confidence: 99%

Calculation and verification of neutron irradiation damage with differential cross sections

Chen

Bernard

Tamagno

et al. 2019

Nuclear Instruments and Methods in Physics Research Section B:

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“…On the other side, in the future, ITER will be equipped with a large set of wide-angle infrared and visible cameras outside the bio-shield that image the surface and plasma emission from four mid-plane ports to routinely monitor the in-vessel components. The main function of this diagnostic is the PFCs' protection, but secondary roles with additional cameras will include scientific purposes [17,18]. Soon the final light line splitting and opto-mechanical design in the port cells outside the bioshield, including the filtering capacity and camera specifications, will be decided [19,20].…”

Section: Introductionmentioning

confidence: 99%

Measuring gross beryllium erosion with visible cameras in JET

Cal¹,

Losada²,

Balboa³

et al. 2022

Nucl. Fusion

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Two visible cameras with the same wide-angle view have been used to study the gross beryllium (Be) erosion in JET. An absolutely calibrated spectroscopy system employed in the past for the same object was used to quantitatively infer the camera photon fluxes and also to validate the results. To extract the effective sputtering yield, a simplified method is applied from the quotient of the measured radiances of the D α and the Be II line at 527 nm. The obtained results are in reasonably good agreement with those already published. The main benefit of using cameras is that the global view of the plasma–wall interaction surfaces of the whole vessel is monitored, and the different sources and their wetted areas can be identified and quantified. In addition, the measurement of the particle flux distributions can be used for the validation of three-dimensional erosion-transport codes.

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“…The Port Plugs are water-cooled stainless steel structures designed to host a wide variety of diagnostic systems. Among them, the Equatorial Visible/Infra-Red Wide Angle Viewing System (WAVS) [1] plays a key role in machine protection by providing on-line monitoring of the surface temperature of plasma facing components, in order to avoid excessive heating. In addition to support diagnostics, the Port Plugs shall provide sufficient radiation shielding to attenuate the propagation of the intense, high-energy plasma-neutron flux.…”

Section: Introductionmentioning

confidence: 99%

A Monte-Carlo Benchmark of TRIPOLI-4® and MCNP on ITER neutronics

et al. 2017

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Abstract. Radiation protection and shielding studies are often based on the extensive use of 3D Monte-Carlo neutron and photon transport simulations. ITER organization hence recommends the use of MCNP-5 code (version 1.60), in association with the FENDL-2.1 neutron cross section data library, specifically dedicated to fusion applications. The MCNP reference model of the ITER tokamak, the 'C-lite', is being continuously developed and improved. This article proposes to develop an alternative model, equivalent to the 'C-lite', but for the Monte-Carlo code TRIPOLI-4®. A benchmark study is defined to test this new model. Since one of the most critical areas for ITER neutronics analysis concerns the assessment of radiation levels and Shutdown Dose Rates (SDDR) behind the Equatorial Port Plugs (EPP), the benchmark is conducted to compare the neutron flux through the EPP. This problem is quite challenging with regard to the complex geometry and considering the important neutron flux attenuation ranging from 10 14 down to 10 8 n•cm -2 •s -1 . Such code-to-code comparison provides independent validation of the Monte-Carlo simulations, improving the confidence in neutronic results.

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The ITER Equatorial Visible/Infra-Red Wide Angle Viewing System: Status of design and R&D

Cited by 25 publications

References 3 publications

Calculation and verification of neutron irradiation damage with differential cross sections

Calculation and verification of neutron irradiation damage with differential cross sections

Measuring gross beryllium erosion with visible cameras in JET

A Monte-Carlo Benchmark of TRIPOLI-4® and MCNP on ITER neutronics

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