Francisco Ogando

National Distance Education University | UNED · Department of Energy Engineering

Several important research programs are dedicated to the development of facilities based on deuteron accelerators. In designing these facilities, the definition of a validated computational approach able to simulate deuteron transport and evaluate deuteron interactions and production of secondary particles with acceptable precision is a very import...

LIPAc stands for Linear IFMIF Prototype Accelerator. LIPAc generates a 9 MeV deuteron beam, which is stopped at a beam dump, depositing over 1 MW of thermal power. A water cooling system has been devised for extracting this energy while keeping operational temperatures within range. The existing high neutron fluxes in the beam dump during operation...

The IFMIF-DONES Facility is a unique first-class scientific infrastructure whose construction is foreseen in Granada, Spain, in the coming years. Strong integration efforts are being made at the current project phase aiming at harmonizing the ongoing design of the different and complex Systems of the facility. The consolidation of the Diagnostics a...

IFMIF-DONES plant [1] (International Fusion Materials Irradiation Facility – DEMO Oriented Neutron Source) is currently being developed under the framework of a work package of the EUROfusion Consortium. It will be a facility located at the south of Spain in Granada. Its objective and main goal is the testing and qualification of fusion materials b...

Integration of safety aspects in IFMIF-DONES design is a main objective of EUROfusion and European Commission projects. IFMIF-DONES will be a radioactive facility of the first category, and stringent safety objectives must be achieved and demonstrated. A very low acceptable risk for the worker, the public and the environment is the main principle i...

IFMIF-DONES plant (International Fusion Materials Irradiation Facility-DEMO Oriented Neutron Source) is currently being developed under the framework of a work package of the EUROfusion Consortium. It will be a facility located at the south of Spain in Granada. Its objective and main goal is the testing and qualification of fusion materials by the...

ITER reference MCNP models are the portentous result of years of geometric modelling, and they share the bio-shield as the natural boundary for practical reasons. Models representing the Tokamak, or fractions of it, end in the bio-shield. Those representing the Tokamak Complex start in the bio-shield. Nuclear analysis beyond the bio-shield is of hi...

The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase under the frame of the Broader Approach Agreement between Europe and Japan, accomplished in summer 2013, on schedule, its EDA phase with the release of the engineering design report of the IFMIF pl...

One of the main radiation sources in nuclear facilities, which cause exposure of workers conducting maintenance activities, is the decay of radioactive nuclides. The determination of these radiation fields usually requires both radiation transport and activation calculations. The Direct-one-Step methodology allows obtaining response functions assoc...

ITER is the flagship fusion project, conceived as an experiment to select and develop the technologies for the first demonstration reactor, DEMO. Nuclear analysis is a core discipline in support of the design, commissioning and operation of the machine. To date, it has been conducted with increasingly detailed partial models, which represented toro...

The International Fusion Materials Irradiation Facility (IFMIF) is a projected accelerator-based, D-Li neutron source for fusion reactor materials qualification. LIPAc (Linear IFMIF Prototype Accelerator) is an accelerator aiming to generate a 125 mA, 9 MeV continuous wave deuteron beam, which is currently being commissioned in Rokkasho (Japan) wit...

The International Fusion Materials Irradiation Facility-Demo Oriented NEutron Source (IFMIF-DONES) impinges a beam of 40 MeV deuterons into a liquid lithium target producing highly energetic neutrons to test and predict nuclear damage in structural material candidates for the DEMO fusion reactor. Unavoidable streaming from the target, and interacti...

Keywords: IFMIF DONES Early neutron source Linear particle accelerator High energy beam transport line Preliminary design A B S T R A C T IFMIF-DONES (International Fusion Materials Irradiation Facility-DEMO Oriented Neutron Source) is currently being developed in the frame of the EUROfusion Early Neutron Source work package (WPENS) and will be an...

The neutron fields alter the radioactive inventory of the irradiated materials leading to subsequent decay photon fields. In some cases, these fields are of relevance either intended or undesired, normally involving safety and economics aspects. The determination of these fields can be of paramount complexity if high spatial resolution is required....

The IFMIF-DONES (International Fusion Material Irradiation Facility-DEMO Oriented NEutron Source) facility is being designed with the general objective of providing irradiation of representative samples of power fusion machine materials under prototypical conditions. A linear accelerator will deliver deuterons at high intensity to circulating lithi...

The International Fusion Materials Irradiation Facility (IFMIF) aims to provide an accelerator-based, D-Li neutron source to produce high energy neutrons at enough intensity and irradiation volume for DEMO materials qualification. As part of the Broader Approach (BA) agreement between Japan and EURATOM, the goal of the IFMIF/EVEDA project is to wor...

IFMIF-DONES (International Fusion Materials Irradiation Facility – DEMO Oriented Neutron Source) is currently being developed in the frame of the EUROfusion Early Neutron Source work package (WPENS) and will be an installation for fusion material testing, that will generate a flux of neutrons of 1018m-2s-1 with a broad peak at 14 MeV by Li(d,xn) nu...

IFMIF-DONES (International Fusion Materials Irradiation Facility-DEMO Oriented Neutron Source) is currently being developed in the frame of the EUROfusion Early Neutron Source work package (WPENS). It will be an installation for fusion material testing, that will generate a flux of neutrons of 10 18 m −2 s −1 with a broad peak at 14 MeV by Li(d,xn)...

In this work, the total heating of the ITER superconducting Poloidal Field Coil #2 (PFC #2) has been calculated due to 16N decay photon radiation emitted from the activated water in the Blanket Manifolds, the Chimney pipes and the Tokamak Cooling Water System (TCWS) manifolds. In order to reduce the total nuclear heating of the PFC #2, shielding me...

The methodological approach applied for the nuclear analyses of the IFMIF-DONES facility, developed within the Early Neutron Source (ENS) project of EUROfusion, is presented. It utilizes dedicated tools, developed and adapted to the specific needs and peculiarities of an accelerator based d-Li neutron source. Major elements relate to the simulation...

The detailed shielding analysis has been performed in order to find a configuration of the radiation shielding in the accelerator building necessary for the operation of the Linear IFMIF Prototype Accelerator (LIPAc), which is under construction in Rokkasho, Japan, at the full power of 1.125 MW to satisfy the radiation dose limit prescribed by Japa...

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...

The International Fusion Materials Irradiation Facility (IFMIF) aims to provide an accelerator-based, D-Li neutron source to produce high energy neutrons at sufficient intensity and irradiation volume for DEMO (Demonstration Fusion Power Plant) materials qualification. As part of the Broader Approach agreement between Japan and EURATOM, the goal of...

The planned in situ maintenance tasks in the ITER port interspace are fundamental to ensure the operation of equipment to control, evaluate and optimize the plasma performance during the entire facility lifetime. They are subject to a limit of shutdown dose rates (SDDR) of 100 μSv h⁻¹ after 10⁶ s of cooling time, which is nowadays a design driver f...

The International Fusion Materials Irradiation Facility (IFMIF) aims to provide an accelerator-based, D-Li neutron source to produce high energy neutrons at sufficient intensity and irradiation volume for fusion materials qualification. The LIPAc is a 125 mA 9 MeV continuous wave deuteron accelerator whose components are under construction mainly i...

The role of nuclear data for neutronics analyses of Fusion Technology (FT) facilities is presented in this paper. Nuclear data evaluations of high quality are required for transport simulations, uncertainty assessments, activation and radiation damage calculations affecting the design and performance of the FT facilities, as well as safety, licensi...

Demonstrating tritium self-sufficiency is an important goal of the European tokamak demonstration fusion reactor. Currently four breeder blanket concepts are being considered: the Helium Cooled Pebble Bed (HCPB), Helium Cooled Lithium-Lead (HCLL), Dual Cooled Lithium-Lead (DCLL) and Water Cooled Lithium-Lead (WCLL). Differences in materials and con...

The methodological approach employed for the neutronics in the PPPT (Power Plant Physics and Technology) programme of EUROfusion is presented. It encompasses development works on advanced computational tools and activities related to the nuclear design and performance evaluation of the DEMO power plant including safety, maintenance, and waste manag...

MCUNED code is an MCNPX extension able to handle evaluated nuclear data library for light ion transport simulations. In this work the MCUNED code is improved to describe more accurately the neutron emission during deuteron induced nuclear reaction. This code update consists in introducing a new methodology to take into account the angular distribut...

This paper explores the quality of available activation cross section (XS) data for accurate Shutdown Dose Rate (SDDR) prediction in the ITER Port Cell and Port Interspace areas, where different maintenance activities are foreseen. For this purpose the EAF library (2007 and 2010 versions) has been investigated, as it is typically used by the ITER c...

The aim of this paper is to check the performance of last versions of EAF and TENDL libraries (EAF2007, EAF2010, and TENDL2014) in the prediction of concrete activation under the neutron irradiation environment expected in IFMIF, an accelerator-based neutron source conceived for fusion materials testing. For this purpose Activity and dose rate resp...

Activation inventories, decay heat and radiation doses are important nuclear quantities which need to be assessed on a reliable basis for the safe operation of a fusion nuclear power reactor. The afterheat and activity inventories were shown to be dominated by the Eurofer steel which is the reference structural material for DEMO. The decay heat for...

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 the most relevant features of state-of-the-art R2S systems, novel and unique features have been implemented in R2SUNED to overcome limitations common to the current mesh-based R2S impl...

The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Validation and Engineering Design Activities (EVEDA) phase under the frame of the Broader Approach Agreement between Europe and Japan, accomplished in summer 2013, on schedule, its EDA phase with the release of the engineering design report of the IFMIF pl...

This report describes the numerical methods implemented in the RELAP5, TRAC-BF1, TRAC-PC1 and CATHARE-2 codes. Date: 1998.

The European Fusion Development Agreement (EFDA) recently launched a programme on Power Plant Physics and Technology (PPPT) with the aim to develop a conceptual design of a fusion demonstration reactor (DEMO) addressing key technology and physics issues. A dedicated part of the PPPT programme is devoted to the neutronics which, among others, has to...

This summary presents a project to recast the pilot course on ADS for a Massive Open Online Course (MOOC) environment.

General Co-Chairwoman of the IYNC 2014 Steering Committee THE 8 th INTERNATIONAL YOUTH NUCLEAR CONGRESS Denis JANIN IYNC 2014 Technical Track Chairman 6 -12 July 2014 BURGOS, SPAIN INTERNATIONAL ISSUE Nº 354. SEPTEMBER 2013 Nuclear Spain is not responsible for the opinions expressed by the authors. No article may be reproduced without express permi...

The International Fusion Materials Irradiation Facility (IFMIF) is designed to be a materials irradiation facility where candidate materials to be used in future fusion designs could be tested. IFMIF is based on two high intensity (125 mA) 40 MeV deuteron accelerators which forms the Accelerator Facility. Interactions of these deuterons with surrou...

CRITERIA METHODOLOGY Failure Mode Effects and Criticality Analysis (FMECA) FMECA STEPS AT IFMIF-EVEDA • Identification of the AF system and basic function description; • Identification of the failure modes, their causes and effects, without any safeguard; • Evaluation of hazard sources; • Qualitative assessment of the frequency and severity of the...

IFMIF will be a materials irradiation facility, based on two high intensity (125 mA) 40 MeV deuteron accelerators. Deuterons at this energy interact with matter producing significant secondary particles and material activation. This results in a radiological hazard for workers and public, and also a concern to facility dismantlement considering rad...

During the operation period of IFMIF accelerator, the interaction of radiation with matter can lead to the activation of the accelerator facilities components and systems. Also as a result of maintenance operation and during decommissioning of the installation, significant amounts of radioactive waste are evacuated and shall be managed according to...

Detailed mechanical design of the LIPAc beam dump radiological shielding

A linear momentum conserving interpolation for the electric field in a three-dimensional toroidal particle-in-cell gyrokinetic plasma simulation in a tokamak configuration is found unstable due to the false divergence of E→×B→ flow of particles. A paradigm 8-point finite difference for interpolation of the radial electric field on the poloidal plan...

During the IFMIF/EVEDA phase, a 125 mA and 9 MeV deuterons prototype accelerator will be designed and tested for the final IFMIF project. During operation of the accelerator deuteron losses will occur in several components leading to material activation induced by deuteron and/or by secondary neutrons, depending on its location. This work is focuse...

The safety analysis for the design of the IFMIF accelerator facility is an ongoing task within the IFMIF project, and the radioprotection analysis is one of the main sections of this task. The high energy beam transport line is a very sensitive section since it contains intense radiation sources. This work presents the radiological analysis of its...

Linear IFMIF Prototype Accelerator (LIPAC) is the prototype accelerator of the Engineering Validation and Engineering Design Activities (EVEDA) phase of the International Fusion Materials Irradiation Facility (IFMIF) project. The EVEDA phase is a first IFMIF step devoted to the construction of prototypes of the main units. The deuteron beam of LIPA...

Under the Spanish Breeding Blanket Technology Program TECNO-FUS, a conceptual design of a dualcoolant lithium-lead (DCLL) blanket for DEMO is being revisited. In this work, different shielding candidate materials are assessed in their ability to satisfy the radiation load requirements that must be fulfilled in the toroidal field (TF) coils: absorbe...

During the IFMIF/EVEDA phase, a 125 125 and 9 MeV deuteron prototype accelerator will be designed and tested for the final IFMIF project. Deuteron losses will occur during operation of the accelerator at several components as well as at the beam stopping, leading to material activation induced by deuterons and/or by secondary neutrons, depending on...

A conceptual design of a DEMO fusion reactor is being developed under the Spanish Breeding Blanket Technology Programme: TECNO_FUS based on a He/LiPb dual coolant blanket as reference design option. The following issues have been analyzed to address the demonstration of the neutronic reliability of this conceptual blanket design: power amplificatio...

In the IFMIF-EVEDA accelerator prototype, deuterium is implanted in the components due to beam losses and in the beam dump, where the beam is stopped. The interaction of the deuterons with the deuterium previously implanted leads to the production of neutrons and tritium, which are important issues for radioprotection and safety analysis. A methodo...

In the frame of IFMIF/EVEDA activities, a prototype accelerator delivering a high power deuteron beam is under construction in Japan. Interaction of these deuterons with matter will generate high levels of neutrons and induced activation, whose predicted yields depend strongly on the models used to calculate the different cross sections. A benchmar...

The IFMIF-EVEDA accelerator will be a 9 MeV, 125 mA cw deuteron accelerator prototype for verifying the validity of the 40 MeV accelerator design for IFMIF. A beam dump designed for maximum power of 1.12 MW will be used to stop the beam at the accelerator exit. The conceptual design for the IFMIF-EVEDA accelerator beam dump is based on a conical be...

Some of the current accelerator programs such as TechnoFusion, Spiral2 or EVEDA/IFMIF will use low energy particles such as proton, deuteron and alpha. For these projects, the radioprotection studies require a more reliable prediction of the neutron and photon generated by interaction of these charged particles. In this paper, some developments to....

Some of the current accelerator programs such as TechnoFusion, Spiral2 or EVEDA/IFMIF will use low energy particles such as proton, deuteron and alpha. For these projects, the radioprotection studies require a more reliable prediction of the neutron and photon generated by interaction of these charged particles. In this paper, some developments to...

The assessment of the accuracy of parameters related to the reactor core performance (e.g., keff) and fuel cycle (e.g., isotopic evolution/transmutation) due to the uncertainties in the basic nuclear data (ND) is a critical issue. Different error propagation techniques (adjoint/forward sensitivity analysis procedures and/or Monte Carlo technique) c...

The objective of the Spanish national project TECNO_FUS is to generate a conceptual design of a DCLL (Dual-Coolant Lithium-Lead) blanket for the DEMO fusion reactor. The dually-cooled breeding zone is composed of He/Pb-15.7 6 Li and SiC as liquid metal flow channel inserts. Structural materials are ferritic-martensitic steel (Eurofer-97) for the bl...

This paper describes the local shielding design process of the IFMIF/EVEDA Beam Dump and the most relevant results obtained from the simulations. Different geometries and materials have been considered, and the design has been optimized taking into account the origin of the doses, the effect of the walls of the accelerator vault and the space restr...

The pulsed nature of the irradiation and the high neutron dose are the critical factors in an Inertial Fusion Energy reactor (IFE). The damage that structural materials suffer under these extremes conditions require a careful study and assessment. The goal of our work is to simulate, trough the multiscale modeling approach, the damage accumulation...

The Beam Dump of the IFMIF/EVEDA accelerator prototype needs to fulfil radioprotection requirements. In order to protect workers and public against radiation arising from the Beam Dump, a shielding for this device has been designed. This radiation is generated due to the stopping of the 125 mA and 9 MeV deuteron beam on the copper cone Beam Stop. T...

The beam stop of the IFMIF/EVEDA accelerator will be a copper cone receiving a total power of ~1 MW, coming from 9 MeV D+ at 125 mA. The mechanical stresses in this beam dump (BD) come mainly from the thermal gradients generated in the cone, being related with the power deposition profile. Anomalous situations can lead to variations in this profile...