Radiation levels in the ITER tokamak complex during and after plasma operation

Ghani, Z.; Turner, Andrew; Mangham, Samuel W.; Naish, J.; Lis, M.; Packer, L.W.; Loughlin, M.

doi:10.1016/j.fusengdes.2015.05.019

Cited by 27 publications

(9 citation statements)

References 2 publications

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“…Nonetheless, when using the it, one faces high statistical errors in the Tokamak Complex because the source sampling is limited to the tracks contained in the WSSA file. On the other hand, previous attempts to use probability distribution functions [2] have been affected by the loss of crossed dependencies of the variables, which is a serious limitation. These are of extreme of importance, because the streaming, a locally intense, energetic and collimated radiation, dominates the radiation responses in many cases.…”

Section: Challenges To the Plasma Radiation Source Modellingmentioning

confidence: 99%

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ITER plasma source and building modelling to produce radiation maps

et al. 2018

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The ITER Tokamak Complex is the civil structure that will host the ITER Tokamak and the largest part of the associated systems. The dimensions are 120 m × 80 m × 60 m, built mostly of concrete, with over one thousand penetrations. During ITER operation, a radiation field will spread throughout the complex from diverse radiation sources. It must be characterized to check the compliance with the limits for electronics allocation and human intervention. However, the production of radiation maps in the ITER Tokamak Complex is a task of paramount sophistication due to challenges to adequately model in MCNP the radiation sources involved. In this work, two important methodological upgrades are presented. First, a new MCNP model of the Tokamak Complex, conceived to be computationally stable while capturing a conservative representation of the baseline. Second, a novel approach to model the plasma source, called a mosaic source, allows an unprecedented degree of realism and accuracy in terms of capturing the port specificities. Both represent a step change in the capacity to produce ITER radiation maps with increased reliability, augmenting previous versions. Examples of partial radiation maps are provided considering both methodological upgrades.

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Section: Challenges To the Plasma Radiation Source Modellingmentioning

confidence: 99%

“…A background of previous works [2] have dealt with important questions, like the production of the MCNP models or the modelling of the plasma radiation source. Both were identified as the main challenges to provide with reliable and useful radiation maps in the Tokamak Complex.…”

Section: Introductionmentioning

confidence: 99%

ITER plasma source and building modelling to produce radiation maps

et al. 2018

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“…More recently, most directly related to ITER, but also for DEMO, there has been increasing activity on neutronics analysis for numerous systems, which help to determine neutron and gamma radiation levels during operation, and shutdown dose rates of paramount importance for remote handling operations. These studies include general radiation levels in the ITER complex, vacuum vessel, cable looms, electron cyclotron (EC), ion cyclotron, and neutral beam injection heating systems, the core imaging x-ray spectrometer, and diagnostic port plugs [18][19][20][21][22][23][24][25][26][27]. These studies allow for shielding optimisation and engineering design modifications to minimise the radiation levels for the diverse insulating materials and assess viability.…”

Section: Where We Are Today / the Present Situationmentioning

confidence: 99%

Functional materials for tokamak in-vessel systems—status and developments

2017

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The challenge to be faced in ITER and DEMO, as well as future fusion power plants (PPs), by the insulating (functional) materials for use not only in the magnetic coils and heating systems but for safety and control diagnostics is daunting. The available data on thermomechanical properties (strength, swelling, thermal conductivity) indicate that suitable materials are available for doses >1 dpa. However, for the important physical properties which degrade at far lower doses, data are generally only available for doses 1 dpa, corresponding at most to ITER expectations. To address this, the selection and development of potential radiation hard materials and components for diagnostic, H&CD, and other systems for DEMO and PPs is urgently needed, and will also assist in defining the materials test requirements for materials test reactors and IFMIF. This paper reviews the current data and basic knowledge for materials required for optical, DC electric, and AC/RF dielectric applications. A short discussion of the associated R&D needs/requirements deduced from missing or limited irradiation data is also presented.

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“…The methodological capability of computing radiation maps due to moving radiation sources was proven by previous work 1 . Nonetheless, the remote-handling scenario of In-Vessel components could not be completely represented due to the following reasons:…”

mentioning

confidence: 93%

“…Previous works have addressed this issue 1 , however, new efforts are required due to (i) the need to follow an exhaustive approach regarding radiation sources and cask operations, (ii) the constant evolution of buildings and components designs, and (iii) the improvement of codes and methodologies. OPEN 1 Dept.…”

mentioning

confidence: 99%

Assessment of ITER radiation environment during the remote-handling operation of In-Vessel components with D1SUNED

Martínez-Albertos

Sauvan

Loughlin

et al. 2023

Sci Rep

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During ITER operational life, a remote-handled cask will be used to transfer In-Vessel components to the Hot Cell for maintenance, storage and decommissioning purposes. Due to the distribution of penetrations for system allocation in the facility, the radiation field of each transfer operation presents a high spatial variability; all operations must be studied independently for workers and electronics protection. In this paper, we present a fully representative approach to describe the radiation environment during the complete remote-handling scenario of In-Vessel components in the ITER facility. The impact of all relevant radiation sources during different stages of the operation is addressed. As-built structures and 2020 baseline designs are considered to produce the most detailed neutronics model of the Tokamak Complex, the 400,000-tonne civil structure hosting the tokamak, up to date. Novel capabilities of the D1SUNED code have allowed to compute the integral dose, the dose rate and the photon-induced neutron flux of both moving and static radiation sources. Time bins are included in the simulations to compute the dose rate caused by In-Vessel components at all positions along the transfer. The time evolution of the dose rate is built in video format with a 1-m resolution, especially valuable for hot-spots identification.

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Radiation levels in the ITER tokamak complex during and after plasma operation

Cited by 27 publications

References 2 publications

ITER plasma source and building modelling to produce radiation maps

ITER plasma source and building modelling to produce radiation maps

Functional materials for tokamak in-vessel systems—status and developments

Assessment of ITER radiation environment during the remote-handling operation of In-Vessel components with D1SUNED

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