Persona: Sanz Gozalo, Javier
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Sanz Gozalo
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Javier
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Publicación Shielding conceptual designs of ITER TCP ports to protect electronics(Elsevier, 2022-01-18) Martínez Albertos, Pablo; Pedroche Sánchez, Gabriel; Dremel, M.; Pearce, R.; Loughlin, M.; Le Tonqueze, Y.; Sanz Gozalo, Javier; Juárez Mañas, RafaelCritical electronics of ITER Tokamak, hosted in the shielded corners (SC) of the Tokamak Building (B11), must operate under acceptable neutronic flux conditions (≤10 n⋅cm 2⋅s 1) to minimize single event effects. During machine operation and at lower level (B1), both the Torus Cryopumps (TCP) ports location within B11 and their pumping efficiency constraints are factors contributing to the radiation environment in the SC. Although previous studies have addressed the transmission of radiation out the vessel of TCP ports, none of them have assessed the impact of such radiation beyond the Port Cell. In this work, different TCP shielding configurations were evaluated at B1 level of B11 due to plasma neutrons emerging from the six TCP ports only. MCNP and dedicated computational tools were used to perform the radiation transport calculations. Albeit being a partial study, the examination of the compatibility between the TCP plasma neutron flux and the electronics limit in the SC has been addressed, while considering the combined effect of the shielding design and the building walls, lintels and doors in the results. We present a combined shielding case that reduces the neutron flux to a range of 1.3–9.3 n⋅cm 2⋅s 1 depending on the location, which is compatible with the limit while respecting pumping efficiency and assembly difficulty constraintsPublicación Sustaining regional Nuclear Human Capacity Building in Europe(ELSEVIER, 2024) Dieguez Porras, Pedro; Sanz Gozalo, Javier; Cizelj, Leon; Ambrosini, Walter; Pavel, Gabriel Lazaro; https://orcid.org/0000-0002-8038-722X; https://orcid.org/0000-0002-8396-7465Nuclear science, a pillar of human advancement in the last century, contributes significantly to clean energy and advanced medical care worldwide. This work highlights the critical importance of preserving nuclear human capacity in Europe to maintain a robust pool of expertise and nuclear Education and Training (E&T) infrastructure. Since 2000, the Organization for Economic Co-operation and Development - Nuclear Energy Agency (OECD-NEA) has expressed deep concern regarding the potential shortage of human resources in the field of nuclear science. The European Human Resources Observatory for Nuclear (EHRO-N) provided insight into the actual human resource levels needed in the nuclear industry in Europe, and this concern remains prevalent in the international community as of the year 2023, especially considering the projected nuclear power capacity by 2050. Given the distinctive and diverse challenges encountered within Europe, a novel quadrangular analysis model is introduced to facilitate the understanding of the diverse Nuclear Human Capacity Building (NHCB) development scenarios in the region. In the European Union (EU), concerted efforts were initiated in 2003 to establish regional networking activities dedicated to nuclear E&T. Since then, a wide range of nuclear stakeholders, including universities, research centers, industry representatives, technical support organizations, and regulatory bodies, have come together in a bottom-up approach to tackle the different NHCB scenarios in Europe, challenged by a variety of public acceptance, a weakly coordinated nuclear policy top-down approach and the cyclical demand of human capital caused by nuclear construction projects. Their collective goal has been to shape a European nuclear E&T ecosystem capable of addressing potential gaps in human resources within the European region. Drawing from the accumulated experience of coordinated European nuclear E&T and knowledge management projects, primarily funded by Euratom, a human-centered and generic NHCB Regional Collaboration Framework Model is proposed to support future coordination efforts in this scientific ecosystem. It is designed to serve as a communication tool for both top-down and bottom-up initiatives from governments, public and private institutions in the EU. The insights and know-how developed by the nuclear E&T community extend beyond their specific domain, offering valuable lessons to the broader nuclear scientific community as well as other industries facing similar challenges in attracting, retaining, and developing human talent.Publicación Preliminary nuclear analysis of HYLIFE-III: A thick-liquid-wall chamber for inertial fusion energy(ELSEVIER, 2024-05) Ogando Serrano, Francisco M.; Tobin, Michael T.; Meier, Wayne R.; Farga Niñoles, Gonzalo; Marian, Jaime; Reyes, Susana; Sanz Gozalo, Javier; Galloway, Conner D.This paper provides neutronics analyses of the Xcimer Energy Corporation (XEC) HYLIFE-III Inertial Fusion Energy Power Plant concept. This design is based on the thick-liquid-wall HYLIFE-II reactor, but with much larger fusion yield, due to enhanced driver energy. Although HYLIFE-II neutronics was extensively studied, the differences between the two concepts suggested new analyses are required. Further, computational advances in neutronics calculations also motivate updating results from more than 25 years ago. The neutron spectra emitted from the much larger yield hybrid Inertial Confinement Energy (IFE) target is presented. Selected breeding materials are compared by tritium breeding ratio (TBR), activation, and first wall protection where FLiBe is proposed as the overall best choice. The first wall neutron activation and structural damage, including gas generation in the wall, is presented for various FLiBe protective wet-wall thicknesses. Final optic neutron damage is also examined and results in optics long enough lifespan with moderate annealing temperatures. Some limited comparisons of first wall damage for ICF and Magnetic Confinement Fusion relevant conditions is presented. HYLIFE-III with FLiBe as the breeding material and first wall protection provides a very robust TBR above 1.2.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.