Titanium Tritide Films as Betavoltaic Power Sources

Ellis, Brian L.; Fritzsche, H.; Patel, Jay B.; Lang, Julien; Suppiah, S.

doi:10.1080/15361055.2017.1290952

Cited by 11 publications

(13 citation statements)

References 20 publications

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“…C409 has the highest

P_{β^{-}}

and P e,vol (1‐ and 100‐μm‐thick 4H‐SiC layers) of all simulated compounds described in this paper. Most importantly, C401, C405, and C409 have a greater P e,vol than Ti 3 H 1.6 and Ti 3 H 2 based on 100‐μm‐thick 4H‐SiC layers, which can currently be produced with the Smart Cut (also Smart cut or Smart‐Cut) process . C405 was picked as the simulated tritiated compound because its bulk density of 0.5 g/cm 3 is close to the experimental bulk‐density range of approximately 0.27 to 0.76 g/cm 3 when deposited on Si rectangular‐pillar array surface, respectively (Figures and ) .…”

Section: Resultsmentioning

confidence: 99%

“…Therefore, the numerical method could then be used to model other tritiated compounds that are either in the beginning stages of development or presently theoretical. Ti 3 H x was chosen because it has an extensive amount of research and development in the past 50 years . Kavetsky et al formulated the beta‐flux surface power density (

P_{β^{-}} ((), D_{L}), ([], \frac{W}{c m^{2}})

) on the surface of a planar source and beta‐source efficiency ( η β , [%]) of Ti 3 H 2 equations based on empirical data .…”

Section: Approachmentioning

confidence: 99%

“…Although the research work of Kavetsky et al uses a fully tritiated titanium tritide (Ti 3 H 2 ), this metal tritide is only stable (presenting negligible tritium‐gas leakage) when the foil or deposited layer is partially tritiated at a maximum range of 81% to 83% loaded. With deuterium ( 2 H 2 ), Ellis et al was able to load the titanium foils to 90% (Ti 2 H 1.8 ), but after 52 days, it dropped to 75% (Ti 2 H 1.5 ) . Thomas et al constructed a nuclear battery with a titanium tritide that was 81% to 83% loaded (Ti 3 H 1.6 to Ti 3 H 1.66 ) while remaining stable .…”

Section: Approachmentioning

confidence: 99%

“…The fully tritiated titanium tritide chemical composition is Ti 3 H 2 ; however, a stable version of this compound has never been created because of tritium desorption in a short timeframe . For example, Ellis et al measured a deuterium loss of 19% (Ti 2 H 2 to Ti 2 H 1.6 ) after a week at SATP and additional deuterium loss of 6% (Ti 2 H 1.6 to Ti 2 H 1.5 ) after 4 days . This experiment shows that deuterium loss is comparable with tritium loss.…”

Section: Approachmentioning

confidence: 99%

“…With deuterium ( 2 H 2 ), Ellis et al was able to load the titanium foils to 90% (Ti 2 H 1.8 ), but after 52 days, it dropped to 75% (Ti 2 H 1.5 ). 24 Thomas et al constructed a nuclear battery with a titanium tritide that was 81% to 83% loaded (Ti 3 H 1.6 to Ti 3 H 1.66 ) while remaining stable. 4 Based on previous work, Ti 3 H 2 and Ti 3 H 1.6 models were constructed using constant mass density of 3.91 g/cm 3 instead of a mass-density gradient from 3.92 g/cm 3 to 4.1 g/cm 3 for both titanium tritide foils.…”

Section: Numerical and Experimental Comparison With Titanium Tritidementioning

confidence: 99%

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Planar and textured surface optimization for a tritium‐based betavoltaic nuclear battery

et al. 2019

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Summary Remote, terrestrial, and space sensors require sources that have high enough power and energy densities for continuous operation for multiple decades. Conventional chemical sources have lower energy densities and lifetimes of 10 to 15 years depending on environmental conditions. Betavoltaic (βV) nuclear batteries using β‐‐emitting radioisotopes possess energy densities approximately 1000 times greater than conventional chemical sources. Their electrical power density (Pe,vol in W/cm3) in a given volume is a function of β‐‐flux surface power density ()Pβ−, surface interface type between radioisotope and transducer, β‐ range, and transducer thickness and conversion efficiency (ηs). Tritium is the most viable β‐‐emitting radioisotope because of its commercial availability, low biotoxicity, half‐life, and low energy, which minimizes the penetration depth and damage of transducer. To maximize Pe,vol, tritium in solid or liquid form must be used in the βV nuclear battery. A Monte Carlo source model using MCNP6 was developed to maximize the Pe,vol of a tritium‐based βV nuclear battery. First, a planar coupling configuration with different tritiated compounds (ie, titanium tritide and tritiated nitroxide) and a semiconductor transducer (4H‐SiC) with thicknesses of 1 and 100 μm were modeled. The results showed that β‐‐source efficiency (ηβ), which is the percentage of energy deposited in the transducer, decreased as the tritiated compound's mass density increased. The highest Pe,vol was dependent on a combination of characteristics: specific activity (Am in Ci/g), mass density, and 4H‐SiC layer thickness. The tritiated nitroxide with the highest Am at 2372 Ci/g produced the highest Pe,vol at 2.46 mW/cm3. Second, a 3‐D coupling configuration was modelled to increase surface interfacing between the radioisotope source and textured transducer surface. 3‐D coupling configuration increased the percentage of energy deposited into the transducer because of more surface interfacing between the transducer and source in the same volume. The tritiated nitroxide was selected as the radioisotope source coupled with five different textured surface feature types. The Pe,vol as a function of textured surface feature and gap, where the radioisotope is located, width was calculated for 1‐ and 100‐μm 4H‐SiC layer thicknesses. Results showed that ηβ increased compared with planar coupling configuration (ie, approximately 56.2% increase over planar with cylindrical hole array) except with the rectangular pillar array. Still, the rectangular pillar array produced the highest Pe,vol at 4.54 mW/cm3 with an increasing factor of 2.29 compared with the planar coupling configuration.

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“…C409 has the highest

P_{β^{-}}

Section: Resultsmentioning

confidence: 99%

P_{β^{-}} ((), D_{L}), ([], \frac{W}{c m^{2}})

) on the surface of a planar source and beta‐source efficiency ( η β , [%]) of Ti 3 H 2 equations based on empirical data .…”

Section: Approachmentioning

confidence: 99%

Section: Approachmentioning

confidence: 99%

Section: Approachmentioning

confidence: 99%

Section: Numerical and Experimental Comparison With Titanium Tritidementioning

confidence: 99%

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Planar and textured surface optimization for a tritium‐based betavoltaic nuclear battery

et al. 2019

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Nuclear batteries: Current context and near‐term expectations

Terranova

2022

Intl J of Energy Research

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Summary The batteries fuelled by radio‐isotopes have represented a significant technological solution for planetary science and exploration missions since the beginning of the space era. Now emerging researches and new concepts are making the nuclear batteries attractive also for relevant terrestrial applications. The present survey aims to summarize the evolution of technical programmes and to examine the multidisciplinary skills required to accelerate the transition of nuclear batteries from laboratory prototypes to fully functional systems.

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Physical viability for nuclear batteries

Tavares,

Terranova

2023

J Radioanal Nucl Chem

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Titanium Tritide Films as Betavoltaic Power Sources

Cited by 11 publications

References 20 publications

Planar and textured surface optimization for a tritium‐based betavoltaic nuclear battery

Planar and textured surface optimization for a tritium‐based betavoltaic nuclear battery

Nuclear batteries: Current context and near‐term expectations

Physical viability for nuclear batteries

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