A5001421060- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Fusion materials and technologies
- Magnetic confinement fusion research
- Graphite, nuclear technology, radiation studies
- Nuclear and radioactivity studies
- Superconducting Materials and Applications
- Nuclear Materials and Properties
- Radiation Detection and Scintillator Technologies
- Radiation Therapy and Dosimetry
- Non-Destructive Testing Techniques
- Nuclear Engineering Thermal-Hydraulics
- Mechanical Engineering and Vibrations Research
- Metallurgy and Material Forming
- Electrostatic Discharge in Electronics
- Material Properties and Applications
- Particle accelerators and beam dynamics
- Geophysical Methods and Applications
National University of Distance Education
2018-2024
Universidad Politécnica de Madrid
2024
Abstract In 2021 JET exploited its unique capabilities to operate with T and D–T fuel an ITER-like Be/W wall (JET-ILW). This second major campaign (DTE2), after DTE1 in 1997, represented the culmination of a series enhancements—new fusion diagnostics, new injection capabilities, refurbishment plant, increased auxiliary heating, in-vessel calibration 14 MeV neutron yield monitors—as well as significant advances plasma theory modelling community. DTE2 was complemented by sequence isotope...
The GEOUNED code is specifically designed to convert CAD models, defined using the B-rep approach, into MC radiation transport CSG and vice versa from CAD. This incorporates standard features commonly found in conversion tools, including decomposition, conversion, automatic void generation. Additionally, it introduces innovative features, mainly generation part, which are described this article. has demonstrated successful application highly detailed 3D models used fusion neutronics, known...
Abstract There is no doubt about the interest of achieving as fast possible capability to build and operate high performance reactors that finally allow fusion competing in electricity market. An advanced breeding blanket based on Dual Coolant Lithium Lead concept with single module segment architecture, designed for European DEMO, certainly aligned such objective. This work describes some recent outcomes efforts carried out framework Prospective R&D Work Package EUROfusion develop this...
The operation of the Wendelstein 7-X has highlighted stellarators as potential fusion power reactors. As a consequence, pre-conceptual design next HELIAS stellarator started in framework EUROfusion. During these first stages, it is essential to assess feasibility various concepts. It important emphasize that concepts can vary significantly terms their overall shape and allocation space for each component, including vacuum vessel, breeding blankets, among others. Although neutronic analysis...
Abstract This contribution presents neutron transport studies for the 5-period helical-axis advanced stellarator using Serpent2 code. These utilize a parametric geometry model, enabling scans in neutronics modeling by varying thickness of reactor layers. For example, tritium breeding ratio (TBR) can be determined exploring various blanket material options and thicknesses to identify threshold configuration that meets TBR design criterion 1.15. We found out with helium-cooled pebble ped...
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...
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...
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...
Under the ambitious EUROfusion mission of "bringing stellarator line to technological maturity", development a Dual Coolant Lithium–Lead (DCLL) Breeding Blanket (BB) for Helical-Axis Advanced Stellarator (HELIAS) started. The BB is crucial systems achieve tritium self-sufficiency in fusion power plants. DCLL has potentialities answer challenges posed by complex HELIAS configuration, having liquid breeder and decoupled first wall (FW) breeding zone circuits. Both characteristics are being...
The stellarator concept is a promising candidate for steady-state fusion power plant, but currently lacking behind the tokamak developments. In order to bring maturity, new EUROfusion Task has been established within Work Package Prospective Research & Development (WP-PRD) called Stellarator Power Plant Studies (SPPS). This task addresses stellarator-specific engineering aspects relevant on way reactor. paper reports strategy of this and provides an overview over ongoing activities as well...
Nuclear analysis of fusion facilities, especially in the context ITER, is complex due to need for precise modeling geometry and radiation sources. Monte Carlo (MC) codes, such as MCNP, are used this their high precision capability deal with these cases. To speed up calculations, variance reduction (VR) techniques crucial carrying out simulations reasonable times. Particularly, cases where only a small source phase space contributes significantly tally must be optimized by an exhaustive...
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...
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,...
Two-step Monte Carlo (MC) neutronic simulations are widely used for nuclear analyses required in fusion facilities. This is the case of ITER beyond bio-shield, where it necessary to couple two models (Tokamak and Tokamak Complex) which share bio-shield as a common interface. Here, radiation transport performed through characterization field that relates both models. SRC-UNED code allows coupling MC by defining sampling realistic intermediate sources represent crossing bio-shield....
Abstract In the frame of WPJET3-DT Technology project within EUROfusion Consortium program, neutronics experiments are being carried out in preparation for current deuterium–tritium campaign on JET (DTE2). The conducted to validate codes and tools used ITER, thus reducing related uncertainties associated risks machine operation. Recently, shutdown dose rate (SDR) results 2016 DD have been analyzed using D1S R2S computational methodologies showing relevant differences between provided by both...
<title>Abstract</title> Development of nuclear fusion as a safe and virtually limitless power source receives growing attention in the context looming energy crisis climate change. ITER project stands flagship international advances steadily. Construction Tokamak Complex is nearly finished, assembly core components has started site. In parallel, design getting finalized safety case gets more concrete. Current approaches for radiation demonstration based 3D analysis require sophisticated...