Deuteron beam interaction with lithium jet in a neutron source test facility

Hassanein, A.

doi:10.1016/s0022-3115(96)00266-8

Cited by 10 publications

(6 citation statements)

References 6 publications

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Section: The Lithium Target Facilitymentioning

confidence: 97%

“…The average temperature rise in the liquid is only about 50 K due to (1) the cross flow and its short exposure of 3.3 ms to the two concurrent 5 MW deuteron beams and (2) the high heat capacity of lithium. The beam versus the liquid target interaction has been the subject of careful analysis since FMIT times [67], the results predicting the absence of lithium boiling are backed with recent experiments where proton beam power densities significantly above saturation conditions (>10 14 W m − 2 ) have been reached in flowing lithium at 50m s − 1 without bubbles nucleation) [68]. Computational fluid dynamics (CFD) calculations have been performed temperature is located at the lower edge of the beam footprint, where the lithium has absorbed all the beam energy in a stream wise direction and at Bragg's peak depths, where the centrifugal pressure amounts to about 7 kPa [71,72], which corresponds to a T s of 1304 K. Turbulence is expected to enhance the transfer of heat, but most of the turbulent region is away from the region of higher temperatures thus limiting the effect of turbulent diffusion to a slight increase in the wall temperatures near the exit.…”

Section: The Lithium Target Facilitymentioning

confidence: 98%

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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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Section: The Lithium Target Facilitymentioning

confidence: 97%

Section: The Lithium Target Facilitymentioning

confidence: 98%

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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“…Lower velocities, leading to peak temperatures as high as -600 K where the lithium vapor pressure is -10-6 torr, can be used with minimal evaporation of lithium into the beam line. The computer code HIJET, developed to study the behavior of moving liquid metal targets during high-power beam irradiation q [36], was used for these simulations. ThR_code is part of the general multipurpose HEIGHTS computer simulation package, which was designed to study the various effects of energetic beams or plasma particles in composite and heterogeneous target systems [37].…”

Section: Windowless Target For Heavy Ion Fragmentationmentioning

confidence: 99%

Liquid-lithium cooling for 100-kW ISOL and fragmentation targets

et al. 2002

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Advanced exotic beam facilities that are currently being developed will use powerful driver accelerator for the production of short-lived rare isotopes. Multi-beam-drivers capable of producing high power beams from very light to very heavy ions are now technically feasible. A challenge for such facilities is the development of production targets to be used for a variety of reaction mechanisms with beam powers of about 100 kilowatts. This paper presents engineering concepts that have been developed recently for using liquid lithium coolant for two types of targets, one for use with light-ion beams on high atomic number (Z) targets and the other for heavy-ion beams on low-Z targets.[PACS classification 29.25 .RIIL Sources of radioactive nuclei; 29.25 .-L Particle sources and targets.

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“…Engineering designs have been carried out for stopping 10-MW deuteron beams in windowless flowing liquid lithium targets (12). Pumps for recirculating liquid lithium are commercially available and are quite small compared to those required for similar mass flow rates of helium gas (13).…”

Section: High Power Targetsmentioning

confidence: 99%

An advanced ISOL facility based on ATLAS

Nolen¹,

Shepard²,

Pardo³

et al. 1999

The Eighth International Conference on Heavy-Ion Accelerator Technology

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AbstracL The Argonne concept for an accelerator complex for efficiently producing highquality radioactive beams from ion source energy up to 6-15 MeV/u is described. lle IsotopeSeparator-On-Lme (ISOL) method is used.A high-power driver accelerator produces radionuclides in a target that is closely coupled to an ion source and mass separator. By using a driver accelerator which can deliver a variety of beams and energies the mdionuclide production mechanisms can be chosen to optimize yields for the species of interest. To effectively utilize the high beam power of the driver two-step targetion source geometries are proposed (1) Neutron production with intermediate energy deuterons on a primary target to produce neutron-*38Utarge~and (2) Fragmentation of neutron-rich heavy ion rich fission products in a secondary beams such as '80 in a targetkatcher geometry. Heavy ion beams with total energies in the 1-10 GcV range are also available for radionuclide production via high-energy spallation reactions. At the present time R&D is in progress to develop superconducting resonator structures for a driver Iinac to cover the energy range up to 100 MeV per nucleon for heavy ions and 200 MeV for protons. lhe post accelerator scheme is based on using existing ISOL-type 1+ ion source technology followed by CW Radio Frequency Quadruple (RFQ) accelerators and superconducting linacs including the present ATLAS accelerator. A full-scale prototype of the first-stage RFQ has been successfidly tested with RF at fdl design voltage and tests with ion beams are in progress. A tenchmark beam, '32Sn@ 7 MeV/u, requires two stripping stages, one a gas stripper at very low velocity after the first RFQ section, and one a foil stripper at higher velocity after a superconducting-linac injector.

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Deuteron beam interaction with lithium jet in a neutron source test facility

Cited by 10 publications

References 6 publications

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

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

Liquid-lithium cooling for 100-kW ISOL and fragmentation targets

An advanced ISOL facility based on ATLAS

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