Development and performance of a 14-MeV neutron generator

Vala, S.; Abhangi, M.; Kumar, Ratnesh; Tiwari, Sanat Kumar; Swami, H.L.; Bandyopadhyay, M.

doi:10.1016/j.nima.2020.163495

Cited by 9 publications

(3 citation statements)

References 18 publications

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“…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%

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: Introductionmentioning

confidence: 99%

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

et al. 2023

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“…Similar to the other configurations of that time, the DEMO strategy was to have large high power devices (∼3 GW) by using LTS magnets and a conventional aspect ratio of ∼3. The progress in the domestic fusion research has led to new laboratories for the development and testing of technologies that are relevant for DEMO such as RF and neutral beam heating, pellet injection and pumping, divertor, magnet, blanket, fuel cycle, remote handling, D-T neutron generator, and cryogenics while continuing to work on ITER deliverables [39][40][41][42][43][44][45][46][47][48][49]. The key drivers for a revision of the strategy are cost reduction, construction-time minimization, modularity, smaller units with shared infrastructure, deeper involvement of industries both, in design and in investment and exploitation of innovations in plasma and fusion science.…”

Section: Introductionmentioning

confidence: 99%

“…There has been an initiation of the above activities in the form of creation of several dedicated laboratories at the Institute for Plasma Research, Gandhinagar, India[39][40][41][42][43][44][45][47][48][49]. Some of these have been built for development and testing of systems that are a part of India's in-kind deliverables to ITER.…”

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A staged approach to Indian DEMO

Deshpande,

Maya

2023

Nucl. Fusion

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We present a revised strategy for Indian DEMO in the context of new technologies and concepts in fusion research. The central idea behind the new strategy is that the power plant is a reactor-park consisting of multiple, preferably compact, reactors with moderate fusion power ($\sim$ 1000 MW) with 35~\% to 50 \% availability for each. The DEMO is a single net electricity producing unit that becomes the basis for replication into multiple units on a commercial scale. One of the key enablers for the revised strategy is the emergence of high-temperature superconductors for high field magnets. For a steady-state burn we show that there exists an optimum regimeof plasma β and confinement where the fusion gain is maximum. Thus, we adopt a strategy with moderate confinement regimes and plasma $\beta$. This makes current drive a necessity for the reactors. Based on these considerations a four-stage approach to DEMO is proposed. It is argued that an electricity producing pilot plant with fusion power of 200 MW - 300 MW is needed before the DEMO to establish the power performance, tritium breeding and its re-use over sufficiently long pulses. An integrated test facility must precede the pilot to test and qualify the technologies for the pilot stage. The revised approach takes into account realistic assumptions on power balance, current drive efficiency and magnet lifetime-dose; factors that pose constraints in identifying potential reactor configurations. Parameter choices for possible options for the integrated test facility (Fusion Engineering Science and Test - FEST), pilot plant and DEMO are presented that can be used to initiate conceptual designs and directed R\&D.

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