Development of tritiated nitroxide for nuclear battery

Russo, Johnny; Litz, Marc; Ray, William B.; Rosen, Gerald M.; Bigio, David I.; Fazio, Robert

doi:10.1016/j.apradiso.2017.04.013

Cited by 21 publications

(15 citation statements)

References 12 publications

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“…26 Tritiated nitroxide Compounds 1 and 2 (C1 and C2) were tritiated, stable, and demonstrated as radioisotope sources for a βV nuclear battery with using 4H-SiC βV cells. 19,20 The last set of numbers represents the bulk or true mass density of tritiated nitroxide C3 and C4. Different densities of the two tritiated nitroxides were simulated and analyzed because of variations in deposition procedure.…”

Section: Numerical Methods Of Planar (2-d) Coupling Configurationmentioning

confidence: 99%

“…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 . 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

D_{opt} = D_{L} ([], {((), 2 P_{β^{-}} * η_{β})}_{italicmax}),

D_{0.99} = D_{L_{n}} ([], 100 % - \frac{2 {P_{β^{-}}}_{n} - 2 {P_{β^{-}}}_{n - 1}}{2 {P_{β^{-}}}_{n}} \approx 99 %),

where n is the counter or index number for the tritiated compound thickness input, D L is the radioisotope layer thickness,

2 P_{{β^{-}}_{n}}

is the bidirectional β ‐ ‐flux surface power density of

D_{L_{n}}

for which

D_{L_{n}}

equals D 0.99 , and

2 {P_{β^{-}}}_{n - 1}

is the bidirectional β ‐ ‐flux surface power density of the previous tritiated compound thickness input,

D_{L_{n - 1}}

.…”

Section: Approachmentioning

confidence: 99%

“…C3 and C4 have already been hydrogenated and deuterated . Tritiated nitroxide Compounds 1 and 2 (C1 and C2) were tritiated, stable, and demonstrated as radioisotope sources for a βV nuclear battery with using 4H‐SiC βV cells . The last set of numbers represents the bulk or true mass density of tritiated nitroxide C3 and C4.…”

Section: Approachmentioning

confidence: 99%

“…In this research we have worked on each described category and related our results to previous research, both experimental and numerical results. Starting with 3) we have identified two tritiated nitroxide compounds based on previous compounds with higher A m and lower mass densities than titanium tritides. In 1) these tritiated nitroxide compounds were compared with Ti 3 H x in planar coupling configuration using our numerical method.…”

Section: Introductionmentioning

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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Section: Numerical Methods Of Planar (2-d) Coupling Configurationmentioning

confidence: 99%

D_{opt} = D_{L} ([], {((), 2 P_{β^{-}} * η_{β})}_{italicmax}),

D_{0.99} = D_{L_{n}} ([], 100 % - \frac{2 {P_{β^{-}}}_{n} - 2 {P_{β^{-}}}_{n - 1}}{2 {P_{β^{-}}}_{n}} \approx 99 %),

where n is the counter or index number for the tritiated compound thickness input, D L is the radioisotope layer thickness,

2 P_{{β^{-}}_{n}}

is the bidirectional β ‐ ‐flux surface power density of

D_{L_{n}}

for which

D_{L_{n}}

equals D 0.99 , and

2 {P_{β^{-}}}_{n - 1}

is the bidirectional β ‐ ‐flux surface power density of the previous tritiated compound thickness input,

D_{L_{n - 1}}

.…”

Section: Approachmentioning

confidence: 99%

Section: Approachmentioning

confidence: 99%

Section: Introductionmentioning

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 have potential uses as power supplies in micro‐electromechanical systems (MEMS) due to their high energy density, stability, and long life . For these reasons, they have received considerable research attention .…”

Section: Introductionmentioning

confidence: 99%

Use the Indirect Energy Conversion of the Phosphor Layer to Improve the Performance of Nuclear Batteries

et al. 2018

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The GaAs X-ray nuclear battery without and with the phosphor layer was investigated under the irradiation of the X-ray tube. The output power was significantly improved by introducing ZnS : Cu or (Zn,Cd)S : Cu phosphor layer, but not by ZnS : Ag phosphor layer because of the degree of spectral matching between the phosphor layer and the GaAs device. To analyze the radioluminescence (RL) effects of the phosphor layers under X-ray excitation, we measured the RL spectra of the different phosphor layers. The RL spectra of the different phosphor layers revealed their fluorescence in the wavelength range of approximately 375-675 nm. Light at the exact wavelength can be used by the GaAs device to produce electricity. Considering irradiation damage of ZnS : Cu phosphor layer induced by X-rays, an additional experiment was carried out to examine irradiation damage of ZnS : Cu. The results indicate that irradiation effect on the RL performance of ZnS : Cu was not obvious.

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In‐Depth Analysis of the Internal Energy Conversion of Nuclear Batteries and Radiation Degradation of Key Materials

Jiang

Meng

et al. 2020

Energy Tech

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Low conversion efficiency and energy output are the main factors hindering the application of the radioluminescent nuclear battery in space. This study analyzes the energy conversion process and proposes a solution of performance promotion. It is found that the energy conversion efficiency of the photovoltaic units is enhanced with increasing incident light intensity. The efficiency of the AlGaInP unit is stable at 22% when the incident energy is at least 3 μW. As for the GaAs unit, the incident threshold value of the photovoltaic response sensitivity is greater than 120 μW. The overall efficiency of the radioluminescent nuclear battery is only 0.37%, consisting of an AlGaInP unit loaded with a low activity 63Ni and the ZnS:Cu phosphor layer. The efficiency increases to 0.87% when an electron radiation source with 270.27 mCi cm−2 is adopted. Moreover, the intense intensity source constitutes an extremely electromagnetic pulse radiation environment, which cause the batteries to fail. The radiation damage is introduced to the phosphor layer by radiation sources, producing agglomerations and cracks on the surface and resulting in the transmittance reduction. This study provides guidance for improving the electrical property and optimization solutions of radioluminescent nuclear battery.

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Development of tritiated nitroxide for nuclear battery

Cited by 21 publications

References 12 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

Use the Indirect Energy Conversion of the Phosphor Layer to Improve the Performance of Nuclear Batteries

In‐Depth Analysis of the Internal Energy Conversion of Nuclear Batteries and Radiation Degradation of Key Materials

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