Towards the EU fusion-oriented neutron source: The preliminary engineering design of IFMIF-DONES

Bernardi, D.; Arbeiter, Frederik; Cappelli, Mauro; Fischer, U.; García, A. R.; Heidinger, R.; Królas, W.; Martín-Fuertes, F.; Miccichè, G.; Muñóz, A.; Nitti, Francesco; Pérez, Mario; Pinna, T.; Tian, Kuo; Ibarra, Á.

doi:10.1016/j.fusengdes.2018.12.042

Cited by 28 publications

(11 citation statements)

References 13 publications

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“…The European strategy for the realisation of fusion energy, as expressed in the recent fusion roadmap [9], is built on three main pillars: the international ITER tokamak to demonstrate the scientific and technological feasibility of fusion as an energy source, an accelerator based neutron source, called IFMIF-DONES [11], for the development and qualification of fusion materials and a DEMOnstration power plant (DEMO) [10], which shall deliver a substantial amount of electricity to the grid and operate with a closed tritium fuel cycle. Neutronics simulations play a fundamental role for the design and optimisation of these facilities, including the evaluation and verification of their nuclear performance.…”

Section: Fusion Applicationsmentioning

confidence: 99%

“…JEFF-3.3 developments targeted the needs for the following reactor development programmes: ASTRID, a French fast reactor concept with enhanced sustainability and safety and reduced production of high level nuclear waste [6], MYRRHA, a research reactor developed in Belgium, advancing and promoting the development of accelerator driven systems and lead or lead-bismuth cooled fast reactors [7,8], and the ITER and DEMO [9,10] reactors and the IFMIF-DONES material irradiation facility [11] in support to nuclear fusion technology. JEFF-3.3 also aims at maintaining or improving performance for present and prospective pressurised water reactors (PWR) and boiling water reactors (BWR) for which JEFF-3.1.1 and JEFF-3.2 demonstrated excellent performance.…”

Section: Introductionmentioning

confidence: 99%

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The joint evaluated fission and fusion nuclear data library, JEFF-3.3

et al. 2020

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The joint evaluated fission and fusion nuclear data library 3.3 is described. New evaluations for neutroninduced interactions with the major actinides 235 U, 238 U and 239 Pu, on 241 Am and 23 Na, 59 Ni, Cr, Cu, Zr, Cd, Hf, W, Au, Pb and Bi are presented. It includes new fission yields, prompt fission neutron spectra and average number of neutrons per fission. In addition, new data for radioactive decay, thermal neutron scattering, gamma-ray emission, neutron activation, delayed neutrons and displacement damage are presented. JEFF-3.3 was complemented by files from the TENDL project. The libraries for photon, proton, deuteron, triton, helion and alpha-particle induced reactions are from TENDL-2017. The demands for uncertainty quantification in modeling led to many new covariance data for the evaluations. A comparison between results from model calculations using the JEFF-3.3 library and those from benchmark experiments for criticality, delayed neutron yields, shielding and decay heat, reveals that JEFF-3.3 performes very well for a wide range of nuclear technology applications, in particular nuclear energy.

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Section: Fusion Applicationsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

et al. 2020

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“…The remainder of the initial projectile continues past the target) reactions and to include it in the project launched in the early 2000s known as IFMIF. The objective of this project is to deepen the knowledge of the behavior of the materials required for the construction of a future fusion reactor [ 125 , 126 , 127 ].…”

Section: Ifmif-donesmentioning

confidence: 99%

“…For this energy production to be possible and profitable, it is necessary to develop materials capable of resisting high energy neutrons and high heat flux to be used in the FW and the blanket. Thus, testing materials and different blanket concepts in a fusion environment is an indispensable step for DEMO design [ 127 ].…”

Section: Ifmif-donesmentioning

confidence: 99%

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Alba¹,

Rodríguez²,

Cerdeira³

2022

Materials

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This paper presents the roadmap of the main materials to be used for ITER and DEMO class reactors as well as an overview of the most relevant innovations that have been made in recent years. The main idea in the EUROfusion development program for the FW (first wall) is the use of low-activation materials. Thus far, several candidates have been proposed: RAFM and ODS steels, SiC/SiC ceramic composites and vanadium alloys. In turn, the most relevant diagnostic systems and PFMs (plasma-facing materials) will be described, all accompanied by the corresponding justification for the selection of the materials as well as their main characteristics. Finally, an outlook will be provided on future material development activities to be carried out during the next phase of the conceptual design for DEMO, which is highly dependent on the success of the IFMIF-DONES facility, whose design, operation and objectives are also described in this paper.

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“…The IFMIF-DONES (International Fusion Materials Irradiation Facility -DEMO Oriented NEutron Source) [5] is a project of an accelerator based deuterium-lithium neutron source for irradiation of fusion reactor materials. A 125 mA beam of 40 MeV deuterons will strike a liquid Li target and produce an unprecedented high flux of neutrons with energies up to 50 MeV.…”

Section: Introductionmentioning

confidence: 99%

Neutron availability in the Complementary Experiments Hall of the IFMIF-DONES facility

Hirtz¹,

Letourneau²,

Thulliez³

et al. 2022

Preprint

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The IFMIF-DONES facility will be dedicated to the irradiation of structural materials planned for the use in future fusion reactors such as DEMO (Demonstration Fusion Power Plant). The potentialities of the IFMIF-DONES facility to complement its principal purpose by other experiments that would open the facility to other communities is addressed in this work. It concerns a study based on simulations to evaluate the neutronic performances of IFMIF-DONES in an hall dedicated to complementary experiments where neutrons can be transported. With the simple beam tube geometry of 4.5 cm entrance diameter studied in this work we have shown that a collimated fast-neutron beam of about 2 10 10 n/cm 2 /s is available in the hall. Adding a moderator in the hall with neutron extraction lines would allow to get thermal neutron beams of about 10 6 -10 7 n/cm 2 /s for dedicated experiments. The results show that IFMIF-DONES has the potentialities to be a medium-flux neutron facility for most of the neutron applications.

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Towards the EU fusion-oriented neutron source: The preliminary engineering design of IFMIF-DONES

Cited by 28 publications

References 13 publications

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

Materials to Be Used in Future Magnetic Confinement Fusion Reactors: A Review

Neutron availability in the Complementary Experiments Hall of the IFMIF-DONES facility

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