A review of helium–hydrogen synergistic effects in radiation damage observed in fusion energy steels and an interaction model to guide future understanding

Marian, Jaime; Hoang, Tuan L.; Fluss, M. J.; Hsiung, L.M.

doi:10.1016/j.jnucmat.2014.12.046

Cited by 62 publications

(28 citation statements)

References 28 publications

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“…One of the caveats of MFRT, however, appears when dealing with multispecies scenarios -a necessity in fusion materials-because the number of ODEs grows exponentially with the number of distinct chemical species. Recent developments in grouping techniques and (semi)continuous treatments of defect distribution tails have enabled the simulation of He-damage interactions and synergies in Fe and W [227][228][229][230][231]. Clearly, however, more needs to be done to extend numerical simulations to the multispecies paradigm inherent to fusion irradiation of materials.…”

Section: Mean Field Damage Accumulation Calculationsmentioning

confidence: 99%

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Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions

Marian

Becquart

Domain³

et al. 2017

Nucl. Fusion

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126

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Under the anticipated operating conditions for demonstration magnetic fusion reactors beyond ITER, structural and plasma facing materials will be exposed to unprecedented conditions of irradiation, heat flux, and temperature. While such extreme environments remain inaccessible experimentally, computational modeling and simulation can provide qualitative and quantitative insights into materials response and complement the available experimental measurements with carefully validated predictions. For plasma facing components such as the first wall and the divertor, tungsten (W) has been selected as the leading candidate material due to its superior hightemperature and irradiation properties, as well as for its low retention of implanted tritium. In this paper we provide a review of recent efforts in computational modeling of W both as a plasmafacing material exposed to He deposition as well as a bulk material subjected to fast neutron irradiation. We use a multiscale modeling approach-commonly used as the materials modeling paradigm-to define the outline of the paper and highlight recent advances using several classes of techniques and their interconnection. We highlight several of the most salient findings obtained via computational modeling and point out a number of remaining challenges and future research directions.

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Section: Mean Field Damage Accumulation Calculationsmentioning

confidence: 99%

“…An example of SCD simulations of damage accumulation in W under ITER conditions (equatorial plane of first wall), including transmutation He, is shown inFigures 20 and 21[231,233]. The associated size distributions of vacancy clusters (including vacancy-He bubbles) and interstitial clusters (dislocation loops) are shown inFigure.…”

mentioning

confidence: 99%

Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions

Marian

Becquart

Domain³

et al. 2017

Nucl. Fusion

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126

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“…Meanwhile, the nuclear reaction cross‐sectional data can be measured, such as (n, p), (n, t), (n, 3 He), (n, a), and other cross section because of the interaction of high‐energy neutrons with Cu, Fe, W, Ni, etc. Note that these reactions, producing hydrogen, helium, and other gases, are strongly related to the properties and lifetime of the materials in fusion reactor . However, these cross‐sectional data are micro barn in order of magnitude, and it is extremely difficult to verify the data.…”

Section: Experimental Plansmentioning

confidence: 99%

Development of high intensity D-T fusion neutron generator HINEG

2016

Int J Energy Res

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Abstract：A high intensity D-T fusion neutron generator (HINEG) is keenly needed for the research and development (R&D) of nuclear technology and safety of the advanced nuclear energy system, especially for the radiation protection and shielding. The R&D of HINEG includes two phases: HINEG-I and HINEG-II. HINEG-I is designed to have both the steady beam and pulsed beam. The neutron yield of the steady beam is up to 10 12 n/s. The width of pulse neutron beam is less than 1.5 ns. HINEG-I is used for the basic neutronics study, such as measurement of nuclear data, validation of neutronics methods and software, validation of radiation protection and so on. HINEG-II aims to generate a high neutron yield of 10 13 n/s neutrons by adopting high speed rotating tritium target system integrated with jet/spray array enhanced cooling techniques, and can further upgrade to obtain neutron yield of 10 14~1 0 15 n/s by using of accelerators-array in a later stage. HINEG-II can be used for fundamentals research of nuclear technology including mechanism of materials radiation damage and neutronics performance of components, radiation shielding as well as other nuclear technology applications.

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“…Swelling was increased with larger cavities developing with an accompanying increase in microhardness in a ferriticmartensitic steel as compared to displacement damage combined with either helium or hydrogen co-injection alone. From these works and others [26], it is clear that multi-ion beam irradiations facilities are required to capture the synergistic behavior of gas injection and radiation damage that occurs in reactor.…”

Section: Introductionmentioning

confidence: 99%

Multiple ion beam irradiation for the study of radiation damage in materials

Taller

Woodley

Getto

et al. 2017

Nuclear Instruments and Methods in Physics Research Section B:

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a b s t r a c tThe effects of transmutation produced helium and hydrogen must be included in ion irradiation experiments to emulate the microstructure of reactor irradiated materials. Descriptions of the criteria and systems necessary for multiple ion beam irradiation are presented and validated experimentally. A calculation methodology was developed to quantify the spatial distribution, implantation depth and amount of energy-degraded and implanted light ions when using a thin foil rotating energy degrader during multi-ion beam irradiation. A dual ion implantation using 1.34 MeV Fe + ions and energy-degraded D + ions was conducted on single crystal silicon to benchmark the dosimetry used for multi-ion beam irradiations. Secondary Ion Mass Spectroscopy (SIMS) analysis showed good agreement with calculations of the peak implantation depth and the total amount of iron and deuterium implanted. The results establish the capability to quantify the ion fluence from both heavy ion beams and energy-degraded light ion beams for the purpose of using multi-ion beam irradiations to emulate reactor irradiated microstructures.

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A review of helium–hydrogen synergistic effects in radiation damage observed in fusion energy steels and an interaction model to guide future understanding

Cited by 62 publications

References 28 publications

Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions

Recent advances in modeling and simulation of the exposure and response of tungsten to fusion energy conditions

Development of high intensity D-T fusion neutron generator HINEG

Multiple ion beam irradiation for the study of radiation damage in materials

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