Persona: Catalán Pérez, Juan Pablo
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jpcatalan@ind.uned.es
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0000-0001-6599-1720
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Catalán Pérez
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Juan Pablo
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Publicación ACABLoop simulation tool: Improving the activation prediction of flowing PbLi alloy in support of DEMO fusion reactor design(ELSEVIER, 2024) García Camacho, Mauricio; Catalán Pérez, Juan Pablo; Sanz Gozalo, JavierPbLi alloy as breeder material is considered within the EUROfusion Programme in the Water-Cooled Lithium-Lead blanket concept of DEMO fusion reactor. The PbLi travels along loops entering and leaving the Breeding Blanket for recovering the produced tritium, removing generated impurities and activated corrosion products, etc. Prediction of activation-related responses in the flowing PbLi is a key safety issue in support of DEMO design. Traditionally, the activation inventory generated in the flowing PbLi has been calculated considering a simplistic approach, valid only for a pre-conceptual analysis. Additionally, the simulation of some phenomena is not possible when using that simple methodology. ACABLoop has been conceived as a tool to overcome such limitations predicting more realistically the activation of the PbLi alloy, providing all the information related to the generated isotopic inventory in the fluid. Status of ACABLoop development is presented as well as some applications for PbLi activation in DEMO loops, proving its suitability for fusion activation calculations. Additionally, a promising first validation of ACABLoop using a water loop and a D-T fusion neutron spectrum is shown. Last improvements of ACABLoop are devoted to allowing incorporation of CFD information as a tool for increasing the reliability in some specific situations.Publicación Fast generation of parametric neutronic models for stellarators. Coupling HeliasGeom and GEOUNED(ELSEVIER, 2024) Alguacil Orejudo, Javier; Catalán Pérez, Juan Pablo; Palermo, Iole; Sosa, David; Lion, Jorrit; Warmer, F.; Sanz Gozalo, Javier; https://orcid.org/0000-0001-8725-8167; https://orcid.org/0009-0000-5319-5575; https://orcid.org/0000-0002-6249-2368The operation of the Wendelstein 7-X has highlighted stellarators as potential fusion power reactors. As a consequence, the pre-conceptual design of the next HELIAS stellarator has started in the framework of EUROfusion. During these first stages, it is essential to assess the feasibility of various stellarator concepts. It is important to emphasize that these concepts can vary significantly in terms of their overall shape and allocation of space for each component, including the vacuum vessel, breeding blankets, among others. Although pre-conceptual neutronic analysis can be conducted using straightforward yet representative neutronic models, such as simplified multilayer models with minimal geometric details, the intricate shape of stellarators presents challenges to produce them quickly. This issue prevents the effective parametric optimization of the concepts, creating a bottleneck in the design of HELIAS. In order to overcome this problem, we are developing a computational workflow for the fast production of parametric stellarator neutronic MCNP models. This work presents the current status of the scheme composed of two steps: HeliasGeom for the production of parametric multilayer CAD models, and GEOUNED for the translation of these models to MCNP CSG neutronic models.Publicación Development of a methodology to estimate the statistical SDR uncertainty with R2S-UNED(ELSEVIER, 2021) Alguacil Orejudo, Javier; Catalán Pérez, Juan Pablo; Sanz Gozalo, Javier; Sauvan, Patrick; https://orcid.org/0000-0002-9128-8817The Rigorous-Two-Steps (R2S) is one of the most useful methods to estimate the Shutdown Dose Rate (SDR). The most advanced R2S tools couple neutron and photon transport, which are often simulated using Monte Carlo (MC) codes, through an activation simulation using mesh-based techniques to improve the spatial resolution of the neutron flux and the decay gamma source. One of the problems of the methodology is that the statistical uncertainty of the neutron flux due to the MC method used by the transport codes is not considered by most R2S implementations. Consequently, larger tolerance must be assumed affecting to the design of the nuclear facilities. This article describes a scheme allowing the calculation of the SDR statistical uncertainty without any additional assumptions than those used in the R2S methodology. The approach proposed in this article is suitable for cell- and mesh-based R2S implementations. In this work, the methodology was implemented in the R2S-UNED code. The accurate application of the methodology requires the full the neutron flux uncertainty (covariance matrix) as input data. MCNP was modified to calculate this matrix, although, it cannot be calculated for most of the realistic R2S simulations due to its size. If that is the situation, we propose a guideline to reduce the size of the covariance matrix to be calculated according to its element contribution to the SDR. When this guideline cannot be applied, the methodology still allows calculating the upper and lower SDR uncertainty bounds. In this article, the guideline is applied to the calculation of the SDR uncertainty in the computational benchmark of ITER. In addition, we also study the possible impact of the neutron flux correlation degree on the SDR uncertainty in this benchmark.Publicación MCNP model of the ITER Tokamak Complex(Elsevier, 2018-04-11) López Revelles, Antonio Jesús; Catalán Pérez, Juan Pablo; Kolsek, Aljaz; Juárez Mañas, Rafael; Rodríguez García, Raquel; García Camacho, Mauricio; Sanz Gozalo, JavierThe Tokamak Complex will accommodate the ITER tokamak and some of the plant systems needed for the machine operation. In order to obtain radiation maps in the Tokamak Complex, a new MCNP model was released on September 2016. This model, based on a conservative representation of the latest baseline design, represents a version controlled, computationally stable, user-friendly and easy-to-update and maintain MCNP input of the Tokamak Complex. Every modification of the initial CAD models was reviewed, recorded and version controlled. The MCNP model of the Tokamak Complex uses the most stable MCNP geometry implementations, avoiding the use of universes and macrobodies. The input exhibits a low particle loss rate (<10−9) when running in void with a dispersed isotropic source. It is strongly organized and profusely commented. Information about the level, building, room, system and material is provided in the definition of every cell. The 36862 cells and 57085 surfaces are arranged by levels and by buildings. The cells are also arranged by rooms and by systems, resulting in a room-oriented organization of the model, which allows an easy isolation of every room.Publicación ITER plasma source and building modelling to produce radiation maps(IOP Publishing, 2018-09-27) Juárez Mañas, Rafael; Catalán Pérez, Juan Pablo; López Revelles, Antonio Jesús; Sauvan, Patrick; Jakhar, Shrichand; Polunovskyi, Edouard; Loughlin, Michael; Sanz Gozalo, Javier; Ogando Serrano, Francisco M.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.