R. Juárez

ORCID: 0000-0001-7649-202X
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About
Contact & Profiles
Research Areas
  • Nuclear reactor physics and engineering
  • Nuclear Physics and Applications
  • Fusion materials and technologies
  • Graphite, nuclear technology, radiation studies
  • Superconducting Materials and Applications
  • Magnetic confinement fusion research
  • Nuclear and radioactivity studies
  • Nuclear Materials and Properties
  • Radiation Detection and Scintillator Technologies
  • Laser-Plasma Interactions and Diagnostics
  • High-pressure geophysics and materials
  • Radiation Therapy and Dosimetry
  • Laser-induced spectroscopy and plasma
  • Medical Imaging Techniques and Applications
  • Power Systems and Renewable Energy
  • Radiation Effects in Electronics
  • Optimal Power Flow Distribution
  • Pharmaceutical Practices and Patient Outcomes
  • Radioactive contamination and transfer
  • Radiation Dose and Imaging
  • Nuclear Engineering Thermal-Hydraulics
  • Advancements in Semiconductor Devices and Circuit Design
  • Geophysical Methods and Applications
  • Smart Grid Energy Management
  • Microgrid Control and Optimization

Universidad Autónoma de Guerrero
2025

National University of Distance Education
2015-2024

Universidad Michoacana de San Nicolás de Hidalgo
2018

Fusion for Energy
2011-2013

Universidad Politécnica de Madrid
2011

R2SUNED is a code system implementing the mesh-based Rigorous-two-step method for shutdown dose rates calculations, making use of MCNP and ACAB codes. In addition to most relevant features state-of-the-art R2S systems, novel unique have been implemented in overcome limitations common current implementations. One particular interest cell-under-voxel approach intended address issues associated with conventional averaging technique used neutron flux determination. The underlying idea identify...

10.1109/tns.2015.2507138 article EN IEEE Transactions on Nuclear Science 2016-02-01

Abstract During ITER operational life, a remote-handled cask will be used to transfer In-Vessel components the Hot Cell for maintenance, storage and decommissioning purposes. Due distribution of penetrations system allocation in facility, radiation field each operation presents high spatial variability; all operations must studied independently workers electronics protection. In this paper, we present fully representative approach describe environment during complete remote-handling scenario...

10.1038/s41598-023-30534-x article EN cc-by Scientific Reports 2023-03-02

Objetivo: Evaluar la eficacia de intervención educativa en adherencia terapêutica (AT) enfocada al seguimento médico conductual (SMC) para regulación emocional (RE) del sistema (SC) personas con hipertensión arterial sistémica (HAS) comunidades rurales Taxco, México em 2022. Marco Teórico: La enfermería el SMC es esencial desarrollo programas salud, ejerce acciones prioritarias gestión enfermedades crónicas, proporciona cuidados directos y progreso a los pacientes; referente teórico Dorothy...

10.55908/sdgs.v13i1.4267 article ES cc-by-nc Journal of Law and Sustainable Development 2025-01-17

One of the primary goals ITER project is to demonstrate safety characteristics a fusion device, particularly in terms radiation management. Radiation protection during maintenance periods special concern, as personnel performing maintenance‐like activities will be exposed delayed gamma fields from numerous and complex radioactive components. Ensuring safe equipped environment for such objective hot cell. This facility requires extensive design optimization, balancing spatial temporal...

10.1155/er/9222155 article EN cc-by International Journal of Energy Research 2025-01-01

During the plasma pulses, neutron-induced activation of cooling water will produce an important contribution to radiation levels in ITER Tokamak Complex. The resulting field has a complex spatial distribution due combination decay and production radioisotopes intricate lines that feed numerous systems inside outside bio-shield. An accurate estimation is necessary ensure radiological zoning respected. As today, this issue been studied using simple, manually defined geometries with limited...

10.1016/j.fusengdes.2021.112575 article EN cc-by Fusion Engineering and Design 2021-04-29

In nuclear fusion installations, high-energy plasma neutron activates the cooling and breeding fluids, generating a mobile distributed source of radiation. water-cooled reactors, such as ITER DEMO, most concerning radioisotopes present in coolant are 16N 17N. Their prompt emission impacts design, safety, and, ultimately, economics plant it can be dominant radiation regions far from plasma. The flowing condition makes calculation radioisotope concentrations within an irradiated circuit...

10.1016/j.cpc.2023.108807 article EN cc-by Computer Physics Communications 2023-06-03

A new model of a grid-connected photovoltaic (PV) plant suitable for power flow analysis is proposed in this paper. Unlike existing models, the proposal departs from equivalent generator representation PV and based instead on operation control modes panels voltage source converters. The resulting set nonlinear equations assembled together with network's to formulate generalized problem unified frame reference, which efficiently solved by using Newton-Raphson algorithm. complementarity...

10.1109/tpwrs.2018.2817585 article EN IEEE Transactions on Power Systems 2018-03-20

The ITER Tokamak Complex is the civil structure that will host and largest part of associated systems. dimensions are 120 m × 80 60 m, built mostly concrete, with over one thousand penetrations. During operation, a radiation field spread throughout complex from diverse sources. It must be characterized to check compliance limits for electronics allocation human intervention. However, production maps in task paramount sophistication due challenges adequately model MCNP sources involved. In...

10.1088/1741-4326/aadf9c article EN Nuclear Fusion 2018-09-07

ITER reference MCNP models are the portentous result of years geometric modelling, and they share bio-shield as natural boundary for practical reasons. Models representing Tokamak, or fractions it, end in bio-shield. Those Tokamak Complex start Nuclear analysis beyond is high relevance to forecast radiation conditions electrical electronic equipment, well human intervention, affecting both economics safety. Nevertheless, it presents a challenge when dealing with plasma source: source not...

10.1016/j.cpc.2022.108309 article EN cc-by-nc-nd Computer Physics Communications 2022-02-11

During ITER operations, electronics located in the crane hall, which is above tokamak, will be exposed to neutron and photon fields from both plasma activated water. To protect electronics, implementation of dedicated shielding on hall platform bioshield top lid required. The design demands optimisation attending constructability, weight limits, radiation requirements. This work evaluates eight configurations by assessment flux dose accumulated over 4700 h operation at 500 MW for protection....

10.1016/j.fusengdes.2023.113960 article EN cc-by Fusion Engineering and Design 2023-08-16

The ITER equatorial port plugs are submitted to a drained weight limit of 45 T. This limitation can conflict with their radiation shielding demands, although some margin is being discussed. interspaces subject shutdown dose rate 100 µSv h−1 after 106 s cooling time. To meet it, the must show neutron flux attenuation comparable neighborhood, despite considering penetrations host systems. Most this task relies on drawer shield module (DSM). In work, two DSM concepts analyzed perspective:...

10.1088/1741-4326/aaadce article EN Nuclear Fusion 2018-02-08

ITER will be the largest Tokamak in world, and it is expected to produce a total of up 2.8•1027 neutrons during its operation. The infrastructure become radioactive as machine operates, which an aspect that needs considered design planed in-situ maintenance activities. occupational radiation exposure (ORE) must accounted for, ALARA program implemented minimize it. It requires determination analysis shutdown dose rates fields, purpose D1SUNED tool. Common all Direct one-step-based approaches,...

10.1016/j.fusengdes.2021.112646 article EN cc-by Fusion Engineering and Design 2021-05-20

In ITER (Nuclear Facility INB-174), ACPs (Activated Corrosion Products) deposited in the cooling channels will represent a major contribution to radiation field during machine shutdown. The primary circuit includes eight Heat Exchangers (HXs) which host thousands of small pipes so-called bundles, where heat is transferred from secondary and accumulate. accurate calculation associated with these hot spots needed, ensure that radiological zoning respected planned maintenance activities...

10.1016/j.fusengdes.2023.113679 article EN cc-by Fusion Engineering and Design 2023-03-27

Nowadays, the projects LIFE (Laser Inertial Fusion Energy) in USA and HiPER (High Power Laser Energy Research) Europe are most advanced ones to demonstrate laser fusion energy viability. One of main points concern properly achieve ignition is performance final optics (lenses) under severe irradiation conditions that take place facilities. In this paper, we calculate radiation fluxes doses as well radiation-induced temperature enhancement colour centre formation lenses assuming realistic...

10.1088/0029-5515/53/1/013010 article EN Nuclear Fusion 2012-12-19

HiPER (High Power laser Energy Research) is the first European plan for international cooperation in developing inertial fusion energy. ICF activities are ongoing a number of nations and ignition experiments underway at National Ignition Facility (NIF) USA. Although still preparatory phase, it appropriate Europe to commence planning future that leverage demonstration ignition. In this paper we shall detail some key points design. Some main topics architecture presented discussed.

10.1117/12.891244 article EN Proceedings of SPIE, the International Society for Optical Engineering/Proceedings of SPIE 2011-05-05

The goal of the European laser fusion project, is to build an engineering facility for repetitive operation (HiPER 4a) and later a reactor 4b). A key aspect energy final optics. At moment, it based on silica transmission lenses located 8 m away from chamber center. Lens lifetime depends irradiation conditions. We have used 48 MJ shock ignition target calculations. studied thermo-mechanical effects ions X-rays lenses. Ions lead lens melting must therefore be mitigated. On other hand, (~1%...

10.1117/12.876163 article EN Proceedings of SPIE, the International Society for Optical Engineering/Proceedings of SPIE 2011-02-02
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