Tritium target manufacturing for use in accelerators

Bach, P.; Monnin, Carole; Rompay, Marc van; Ballanger, A.

doi:10.1063/1.1395506

Cited by 2 publications

(5 citation statements)

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“…The atoms of these isotopes recombine on the surface and start permeating through the metal depth. Titanium has high hydrogen retention, absorption, and storage characteristics and due to these, it is often used as a base material for hydrogen, deuterium, and tritium storage and Copper is used as a substrate [13]. Tritium loading in the titanium metal is carried out either with electron gun evaporation or with the thermal evaporation methods [13].…”

Section: Methodology and Simulation Detailsmentioning

confidence: 99%

“…Titanium has high hydrogen retention, absorption, and storage characteristics and due to these, it is often used as a base material for hydrogen, deuterium, and tritium storage and Copper is used as a substrate [13]. Tritium loading in the titanium metal is carried out either with electron gun evaporation or with the thermal evaporation methods [13]. The evaporation temperature, the ratio of tritium and titanium atoms, surface area and thickness of titanium metal govern the properties of tritium titanium target and tritium activity associated with it [20,21].…”

Section: Methodology and Simulation Detailsmentioning

confidence: 99%

“…The evaporation temperature, the ratio of tritium and titanium atoms, surface area and thickness of titanium metal govern the properties of tritium titanium target and tritium activity associated with it [20,21]. In this manuscript, we have modelled the commercially produced tritium target from manufacturers such as SODERN, etc [13]. The mass density of TiT 2 target is taken to be 4.09 g cm −3 [22] which corresponds to the atomic density of 1.387 × 10 23 atoms cm −3 .…”

Section: Methodology and Simulation Detailsmentioning

confidence: 99%

“…These 14.1 MeV neutrons are also very useful in medical radioisotope production, fundamental nuclear physics experiments, fast neutron detector development, and neutron imaging tool developments [10][11][12]. Tritium-titanium targets are among such commercially available targets [13][14][15][16] that are used to produce the 14.1 MeV energy neutrons through the 2 H( 3 H,n) 4 He reaction at various laboratories [9,10,17,18]. The interactions of deuterium ions with the tritium-titanium target remove tritium via sputtering, outgassing, diffusion, replacement with deuterium ions, or ion exchange while some fraction of tritium is utilized in the neutron production [19].…”

Section: Introductionmentioning

confidence: 99%

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Tritium-titanium target degradation due to deuterium irradiation for DT neutron production

et al. 2023

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In the present article, we have investigated the tritium removal from the tritium-titanium target during fusion neutron production and impact of tritium degradation on neutron production. The removal of tritium from target is predicted for deuterium ion irradiation with the SDTrimSp code. We adopt the binary collision approximation (BCA) method to simulate the recoils and projectile trajectories and concentration of constituents in the target. We have modelled four phenomena in our simulations; ion exchange, sputtering, outgassing of tritium, and thermal diffusion of hydrogen isotopes in the target caused by the deuterium irradiation. Insignificant contributors as burn-up of tritium in neutron production and loss of tritium due to radioactive decay are not included in our model. This tritium removal results in the nonuniform distribution of tritium in the target. A python-based script is developed to investigate the effects of tritium removal on neutron production with these pristine and irradiated targets. This script uses the layered composition of the constituents' atoms, DT reaction cross section, and stopping power of deuterium ions in the target. This script is validated with the NeuSdesc code for the pristine target. Using the layered composition of tritium atoms in the target obtained from the SDTrimSp simulations, the script predicts the degradation in neutron production for different irradiation scenarios.

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Section: Methodology and Simulation Detailsmentioning

confidence: 99%

Section: Methodology and Simulation Detailsmentioning

confidence: 99%

Section: Methodology and Simulation Detailsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Tritium-titanium target degradation due to deuterium irradiation for DT neutron production

et al. 2023

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“…To make the tritium a solid target, it should be attached with an affinity of titanium metal. The vapour of tritium is deposited on the titanium coating [27]. It will make the deuterium ion transport and interaction different from the simple analytical calculation due to the introduction of another element and taking into account the slowing down of ions in the target.…”

Section: Design Basismentioning

confidence: 99%

Physics design of 14 MeV neutron generator facility at the Institute for Plasma Research

Swami

2023

Plasma Sci. Technol.

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High energy and high yield neutron source is a prime requirement for technological studies related to fusion reactor development. It provides the high energy neutron environment for small-scale fusion reactor components research and testing such as tritium breeding, shielding, plasma-facing materials, reaction cross-section data study for fusion materials, etc. Along with ITER participation, the Institute of Plasma Research, India is developing an accelerator-based 14 MeV neutron source with a yield of 1012 n/s. The design of the source is based on the deuterium-tritium fusion reaction. The deuterium beam is accelerated and delivered to the tritium target to generate the 14 MeV neutrons. The deuterium beam energy and tritium availability in tritium target are the base parameters of the accelerator-based neutron source design. The paper gives the physics design of the neutron generator facility of IPR. It covers the requirements, design basis, and physics parameters of the neutron generator. As per the analytical results generator can produce more than 1x1012 n/s with a 110 keV D+ ion beam of 10 mA and a minimum 5 Ci tritium target. However, the detailed simulation with more realistic condition of deuteron ion interaction with tritium titanium target shows that the desired results cannot be achieved with 110 keV. The safe limit of the ion energy should be 300 keV as per simulation. At the 300 keV ion energy and 20 mA current, it reaches to the 1.6x1012 n/s. Moreover, to enhance the duration of steady state emission rate, the design parameters considered for the generator are 300 keV D+ ion beam with current of 20 mA and tritium target more than 20 Ci. The scope of the neutron source is not limited to the fusion reactor research studies, it is extended to the other area such as medical radioisotopes research, semiconductor devices irradiations, and many more.

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Tritium target manufacturing for use in accelerators

Cited by 2 publications

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Tritium-titanium target degradation due to deuterium irradiation for DT neutron production

Tritium-titanium target degradation due to deuterium irradiation for DT neutron production

Physics design of 14 MeV neutron generator facility at the Institute for Plasma Research

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