3. Selection Requirements for Tissue Substitutes

White, D. R.; Booz, J.; Griffith, R. V.; Spokas, J. J.; Wilson, I. J.

doi:10.1093/jicru_os23.1.14

Cited by 7 publications

(9 citation statements)

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“…The R‐value can be determined based on the photon energy fluence and the mass energy absorption coefficient as expressed by the following formula:

R = Σ ψ false(E false) (\frac{μ_{italicen} (E)}{ρ})

ψ (E)

is the photon fluence as a function of energy per unit cumulative radioactivity in the source organ, and μ en ρ −1 is the mass energy absorption coefficient. The mass energy absorption coefficient can be taken from the International Commission on Radiation Units and Measurements (ICRU) Report 44 (1989), and the photon fluence can be obtained from a Monte Carlo simulation.…”

Section: Methodsmentioning

confidence: 99%

Internal radiation dose estimation using multiple D‐shuttle dosimeters for positron emission tomography (PET): A validation study usingNEMAbody phantom

et al. 2018

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“…The R‐value can be determined based on the photon energy fluence and the mass energy absorption coefficient as expressed by the following formula:

R = Σ ψ false(E false) (\frac{μ_{italicen} (E)}{ρ})

ψ (E)

Section: Methodsmentioning

confidence: 99%

Internal radiation dose estimation using multiple D‐shuttle dosimeters for positron emission tomography (PET): A validation study usingNEMAbody phantom

et al. 2018

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“…In the case of TEPCs, this is typically A150 plastic. This material, like tissue equivalent gas, has a mass stopping power that matches ICRU tissue (ICRU Report 44, White et al, 1989) over a wide, but still limited range of charged particles and energies; therefore, in unusual radiation fields such as high-energy accelerators or space environments, as well as any substitution of the wall-material with another material, stopping power values of the counter wall compared with tissue has to be taken into account. Finally, the simulation principle is not particular to gas detectors alone and is equally applicable to solidstate microdosimeters where the detection medium has a higher density than tissue (see section 8).…”

Section: Experimental Simulation Of Small Sitesmentioning

confidence: 99%

ICRU Report 98, Stochastic Nature of Radiation Interactions: Microdosimetry

Braby,

Conte,

Dingfelder

et al. 2023

J�ICRU

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The Journal of the ICRU publishes reports on important and topical subjects within the field of radiation science and measurement. It is the successor to the series of reports published by or on behalf of the International Commission on Radiation Units and Measurements (ICRU) since 1927. The Commission continually reviews radiation science with the aim of identifying areas where the development of guidance and recommendations can make an important contribution.

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“…The concentration of gadolinium was 18 mg ml −1 . The adipose material properties were collected from ICRU-44 (White et al 1989). A diagram of this sixmaterial problem can be seen in figure 2(a) along with the ROIs used to compute the quantitative results.…”

Section: Six-materials Decompositionmentioning

confidence: 99%

Multi-step material decomposition for spectral computed tomography

2019

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Spectral images from photon counting detectors are being explored for material decomposition applications such as for obtaining quantitative maps of tissue types and contrast agents. While these detectors allow acquisition of multi-energy data in a single exposure, separating the total photon counts into multiple energy bins can lead to issues of count starvation and increased quantum noise in resultant maps. Furthermore, the complex decomposition problem is often solved in a single inversion step making it difficult to separate materials with close properties. We propose a multi-step decomposition method which allows solving the problem in multiple steps using the same spectral data collected in a single exposure. During each step, quantitative accuracy of a single material is under focus and one can flexibly optimize the bins chosen in that step. The result thus obtained becomes part of the input data for the next step in the multi-step process. This makes the problem less ill-conditioned and allows better quantitation of more challenging materials within the object. In comparison to a conventional single-step method, we show excellent quantitative accuracy for decomposing up to six materials involving a mix of soft tissue types and contrast agents in micro-CT sized digital phantoms.

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3. Selection Requirements for Tissue Substitutes

Cited by 7 publications

References 0 publications

Internal radiation dose estimation using multiple D‐shuttle dosimeters for positron emission tomography (PET): A validation study usingNEMAbody phantom

Internal radiation dose estimation using multiple D‐shuttle dosimeters for positron emission tomography (PET): A validation study usingNEMAbody phantom

ICRU Report 98, Stochastic Nature of Radiation Interactions: Microdosimetry

Multi-step material decomposition for spectral computed tomography

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