The IFMIF-EVEDA accelerator beam dump design

Iglesias, Daniel; Arranz, F.; Alguacil, Natalia; Barrera, G.; Brañas, B.; Casal, N.; García, M.; López, Daniel; Martínez, Juana; Mayoral, A.; Ogando, F.; Parro, M.; Oliver, C.; Rapisarda, D.; Sanz, J.; Sauvan, P.; Ibarra, Á.

doi:10.1016/j.jnucmat.2010.12.273

Cited by 18 publications

(7 citation statements)

References 3 publications

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“…For the design of a high-power dump, in addition to analyzing a radiological protection issue, cooling system and mechanical manufacturing of the dump also need to be considered [10][11][12]. As mentioned in beam loss assumption, the power of the three dumps is relatively small, and the maximum power is only 1.875 W. Therefore, the design of the dump here is mainly focused on radiological protection issues.…”

Section: Shielding Design For the Dumpsmentioning

confidence: 99%

Radiation protection designs of the linac for the HEPS

Liu

et al. 2021

Radiat Detect Technol Methods

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Purpose The high-energy photon source (HEPS) is the first fourth-generation light source under construction in China. It is designed to operate at an average current of 200 mA stored beam current with a top-up model at 6 GeV energy. Considering the linac radiation shielding design, a suitable beam loss scenario, optimized thickness for the bulk shielding and detailed structure design for dumps should be proposed. In this paper, the beam loss scenarios were determined and categorized as normal; the dose limits were presented; using these scenarios and the dose limits, the thickness of the linac tunnel was calculated and detailed designs of the main beam dumps were established. The material selection and size setting of the low-power electron beam dump were discussed. Method The Monte Carlo code is a good choice to simulate the radiation analysis. And the iSHIELD11 was used to verify the simulation calculations. Result and conclusionThe designs of the linac bulk shield and dumps satisfied the requirements of radiation protection.

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Section: Shielding Design For the Dumpsmentioning

confidence: 99%

Radiation protection designs of the linac for the HEPS

Liu

et al. 2021

Radiat Detect Technol Methods

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“…As the temperature of the material at the coolant side can reach 120 • C, the water must be slightly pressurized (around 6 bar) to avoid local boiling. The pressure losses along the cone and in the whole circuit have been allowed to be around 2.5 bar respectively, due to physical strength of material parameters chosen [13][14][15].…”

Section: Thermal Analysismentioning

confidence: 99%

Thermal analysis and neutron production characteristics of a low power copper beam dump-cum-target for LEHIPA

et al. 2016

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simulations of heat deposition and neutron production have been carried out for the low power beam dump-cum-target for the 20 MeV Low Energy High Intensity Proton Accelerator (LEHIPA) facility at BARC using GEANT4 and FLUKA. Thermal analysis and heat transfer calculations have also been carried out using the computational fluid dynamics code CFD ACE+. In this work we present the details of the analysis of the low power beam dump-cum-target designed for conditioning of the accelerator upto a maximum power of 600 kW with a duty cycle of 2% which corresponds to an average power of 12 kW in the first phase. K: Targets (spallation source targets, radioisotope production, neutrino and muon sources); Instrumentation for neutron sources; Beam-line instrumentation (beam position and profile monitors; beam-intensity monitors; bunch length monitors) 1Corresponding author.

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“…The high beam current and relative low energy challenges the beam diagnostic that has demanded their specific research programs [52], becoming part of the validation activities [19] and their installation cloned from IFMIF. The main features are the very high intensity beams which, together with the low energy and small material penetration, preclude the use of any interceptive diagnostics during nominal continuous beam operation.…”

Section: The Accelerator Facilitymentioning

confidence: 99%

The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European–Japanese project towards a Li(d,xn) fusion relevant neutron source

Knaster¹,

Ibarra

Abal

et al. 2015

Nucl. Fusion

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The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Validation and Engineering Desi gn 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 plant, which is here described. Many improvements of the design from former phases are implemented, particularly a reduction of beam losses and operational costs thanks to the superconducting accelerator concept, the re-location of the quench tank outside the 1 2 × test cell (TC) with a reduction of tritium inventory and a simplification on its replacement in case of failure, the separation of the irradiation modules from the shielding block gaining irradiation flexibility and enhancement of the remote handling equipment reliability and cost reduction, and the water cooling of the liner and biological shielding of the TC, enhancing the efficiency and economy of the related sub-systems. In addition, the maintenance strategy has been modified to allow a shorter yearly stop of the irradiation operations and a more careful management of the irradiated samples. The design of the IFMIF plant is intimately linked with the EVA phase carried out since the entry into force of IFMIF/EVEDA in June 2007. These last activities and their on-going accomplishment have been thoroughly described elsewhere (Knaster J et al [19]), which, combined with the present paper, allows a clear understanding of the maturity of the European-Japanese international efforts. This released IFMIF Intermediate Engineering Design Report (IIEDR), which could be complemented if required concurrently with the outcome of the on-going EVA, will allow decision making on its construction and/or serve as the basis for the definition of the next step, aligned with the evolving needs of our fusion community.

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The IFMIF-EVEDA accelerator beam dump design

Cited by 18 publications

References 3 publications

Radiation protection designs of the linac for the HEPS

Radiation protection designs of the linac for the HEPS

Thermal analysis and neutron production characteristics of a low power copper beam dump-cum-target for LEHIPA

The accomplishment of the Engineering Design Activities of IFMIF/EVEDA: The European–Japanese project towards a Li(d,xn) fusion relevant neutron source

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