Study of transmutation, gas production, and displacement damage in chromium for fusion neutron spectrum

Rajput, Mayank; Srinivasan, R.

doi:10.1016/j.anucene.2019.107187

Cited by 3 publications

(5 citation statements)

References 29 publications

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“…A significant amount of damage accumulates in structural materials during the lifetime of reactor operation. Besides neutron-induced cascade damage, transmutation produces varying isotopes of various alloying elements including chromium 18 . The high radiation doses coupled with the high temperature during reactor operation leads to degradation of structural material properties, resulting in hardening, embrittlement, creep, and swelling [19][20][21] .…”

Section: Introductionmentioning

confidence: 99%

Three-dimensional strain imaging of irradiated chromium using multi-reflection Bragg coherent diffraction

et al. 2022

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Radiation-induced materials degradation is a key concern in limiting the performance of nuclear materials. The formation of nanoscale void and gas bubble superlattices in metals and alloys under radiation environments can effectively mitigate radiation-induced damage, such as swelling and aid the development of next generation radiation tolerant materials. To effectively manage radiation-induced damage via superlattice formation, it is critical to understand the microstructural changes and strain induced by such superlattices. We utilize multi-reflection Bragg coherent diffraction imaging to quantify the full strain tensor induced by void superlattices in iron irradiated chromium substrate. Our approach provides a quantitative estimation of radiation-induced three-dimensional (3D) strain generated at the microscopic level and predicts the number density of defects with a high degree of sensitivity. Such quantitative evaluation of 3D strain in nuclear materials can have a major impact on predicting materials behavior in radiation environments and can revolutionize design of radiation tolerant materials.

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Section: Introductionmentioning

confidence: 99%

Three-dimensional strain imaging of irradiated chromium using multi-reflection Bragg coherent diffraction

et al. 2022

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“…Nuclear fusion energy is one of the possible alternative energy sources to conventional coal and gas operated power plants and has the potential to provide carbon-free energy in the 3 Present address: Tokamak Energy, Milton Park, Abingdon, United Kingdom of Great Britain and Northern Ireland. * Author to whom any correspondence should be addressed.…”

Section: Introductionmentioning

confidence: 99%

“…Primary fuels for fusion energy are deuterium and tritium. Deuterium can be extracted from sea water and tritium can be bred from the 6 Li(n, 3 H) 4 He and 7 Li(n, 3 H + n) 4 He reactions. One major concern associated with fusion reactors is the handling of 14.1 MeV energy neutrons.…”

Section: Introductionmentioning

confidence: 99%

“…One major concern associated with fusion reactors is the handling of 14.1 MeV energy neutrons. These neutrons are capable of producing gases, radioactive isotopes, and causing displacement damage [2,3], thus affecting the lifetime and functionality of fusion reactor components [4]. From the neutronics point of view, the prime requirements for the successful realisation of fusion power are to have accurate and precise nuclear data for the materials to be used in it [5], to understand the effects of fusion neutrons on reactor components including electronics and structural materials [6] and to investigate tritium breeding capabilities of breeder blankets [7].…”

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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“…A significant amount of damage accumulates in structural materials during the lifetime of reactor operation. Besides neutron-induced cascade damage, transmutation produces varying isotopes of various alloying elements including chromium 24 . The high radiation doses coupled with the high temperature during reactor operation leads to degradation of structural material properties, resulting in hardening, embrittlement, creep, and swelling [25][26][27] .…”

Section: Introductionmentioning

confidence: 99%

Three-dimensional strain imaging of irradiated chromium using multi-reflection Bragg coherent diffraction

Jossou¹,

Assefa²,

Suzana

et al. 2022

Preprint

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Radiation-induced materials degradation is a key concern in limiting the performance of nuclear materials. The formation of nanoscale void and gas bubble superlattices in metals and alloys under radiation environments can effectively mitigate radiation-induced damage, such as swelling and aid the development of next generation radiation tolerant materials. To effectively manage radiation-induced damage via superlattice formation, it is critical to understand the microstructural changes and strain induced by such superlattices. In our approach, we utilize multi-reflection Bragg coherent diffraction imaging (BCDI) to quantify the full strain tensor induced by void superlattices in iron (Fe) irradiated chromium substrate, a model metallic system. Multi-reflection BCDI is a powerful method for detailed investigation of the strain and microstructural changes caused by radiation-induced defects during Fe ion implantation, a key fundamental understanding that is inaccessible via current conventional techniques. Our approach provides a quantitative estimation of radiation-induced three dimensional (3D) strain generated at the microscopic level and predicts the number density of defects with a high degree of sensitivity in bulk metallic substrates. Such quantitative evaluation of 3D strain in nuclear materials can have a major impact on predicting materials performance and degradation in radiation environments and can revolutionize design of radiation tolerant materials.

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Study of transmutation, gas production, and displacement damage in chromium for fusion neutron spectrum

Cited by 3 publications

References 29 publications

Three-dimensional strain imaging of irradiated chromium using multi-reflection Bragg coherent diffraction

Three-dimensional strain imaging of irradiated chromium using multi-reflection Bragg coherent diffraction

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

Three-dimensional strain imaging of irradiated chromium using multi-reflection Bragg coherent diffraction

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