Calculation and benchmark of fluence-to-local skin equivalent dose coefficients for neutrons with FLUKA, MCNP, and GEANT4 Monte-Carlo codes

Frosio, Thomas; Bertreix, Philippe; Menaa, N.; Thomas, Samuel

doi:10.1088/1361-6498/ac057e

Cited by 13 publications

(6 citation statements)

References 13 publications

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“…• The physics models for the transport of charged particles are different for the three codes, as explained in section 2. FLUKA and MCNP use kerma factors to estimate energy deposition by neutrons as it is detailed in [22]. On the other hand, GEANT4 considers a real neutron transport physics model.…”

Section: Resultsmentioning

confidence: 99%

Section: Fluka Simulationsmentioning

confidence: 99%

“…The energy deposition is assessed in FLUKA by means of kerma approximation factors (see FLUKA's manual 4 ). A detailed description of kerma factors impact on deposited energy is available in [22]. More precisely, among the secondary particles originating from primary neutrons, only neutrons, protons (two types) and photons, are transported in FLUKA.…”

Section: Fluka Simulationsmentioning

confidence: 99%

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Skin dose contamination conversion coefficients. Benchmark with three simulation codes

et al. 2021

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Handling of radioactive material by operators can lead to contamination at the surface of the skin in case of an accident. The quantification of the dose received by the skin due to a contamination scenario is performed by means of dedicated dose coefficients as it is the case for other radiation protection dose quantities described in the literature. However, most available coefficients do not match realistic scenarios according to state-of-the-art of science and technology. Therefore, this work deals with dedicated dose conversion factors for skin contamination. Since there is an increasing demand on dose coefficients in general, these specific coefficients can be used for various calculations in radiation protection. In this work a method to evaluate such coefficients for the skin contamination dose related to photons, electrons, positrons, alpha and neutron particles is proposed. The coefficients are generated using Monte-Carlo simulations with three well established calculation codes (FLUKA, MCNP, and GEANT4). The results of the various codes are compared against each other for benchmarking purposes. The new dose coefficients allow the computation of the skin received dose, in the case of skin contamination scenario of an individual, taking into account the decay radiation of the radionuclides of interest. To benchmark the quantity derived here, comparisons of radionuclide contamination doses to the skin using the VARSKIN code available in the literature are performed with the results of this work.

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Section: Resultsmentioning

confidence: 99%

Section: Fluka Simulationsmentioning

confidence: 99%

Section: Fluka Simulationsmentioning

confidence: 99%

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Skin dose contamination conversion coefficients. Benchmark with three simulation codes

et al. 2021

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“…In general, the models agree with each other (for details see Bottollier‐Depois et al., 2009). We emphasize that about 50% of the complex radiation field at aviation altitudes is due to neutrons (e.g., Goldhagen et al., 2004; Gordon et al., 2004; Merker, 1973; Nakamura et al., 1987), where neutrons with energies in the MeV range and above have the greatest biological impact (Baiocco et al., 2016; Frosio et al., 2021; Siebert & Schuhmacher, 1995). Therefore, the proper modeling of secondary neutron flux in the Earth's atmosphere is particularly important (A. Mishev, 2016; Hubert et al., 2016).…”

Section: Cosmic Ray Atmospheric Cascade: Dosimetric Model Crac:domomentioning

confidence: 96%

Relationship Between NM Data and Radiation Dose at Aviation Altitudes During GLE Events

Larsen,

Mishev

2024

Space Weather

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Ground‐level enhancements (GLEs) are sporadic events that signal the arrival of high fluxes of solar energetic particles (SEPs) that have been produced by solar eruptions. Ground‐level enhancement events are characterized by a significant increase in the count rate of ground‐based neutron monitors (NMs). The arrival of high‐energy SEPs in the atmosphere leads to an enhancement of the radiation environment, with the enhancement at aviation altitudes being particularly hazardous to human health as pilots, crew, and airline passengers can be subjected to dangerous levels of radiation during a GLE. Through the use of a currently expanding library of analyzed GLEs and the application of a newly developed atmospheric radiation model, both of which have been created in‐house, we found a strong statistically significant relationship between real‐time NM data during GLE events and the radiation doses at aviation altitudes. This result provides a strong scientific basis for the use of real‐time NM data as a proxy for radiation dose estimates during GLE events and aids in the development of future nowcasting models to help mitigate the dangerous impacts of future GLEs.

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“…This paper focuses on the dose 'transfer functions' that are derived to evaluate Q A , Q B,skin and Q B,eye , which respectively represent the total effective dose, total equivalent dose to the skin and total equivalent dose to the lens of the eye, for all types of primary and secondary particles contributing to the dose. Other quantities evaluated by the Working Group (Q C , Q D,skin , Q D,ing , Q E ) for the derivation of the A 1 /A 2 values have already been published [16].…”

Section: Introductionmentioning

confidence: 99%

Transfer functions for Q_A /Q_B international regulatory limits for the safe transport of radioactive materials

Frosio,

Thomas,

Endres

et al. 2024

J. Radiol. Prot.

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This paper presents a proposed revision of the International Atomic Energy Agency (IAEA) transport regulations, related to the A1 and A2 limit values used to determine the radioactive transport classification. Based on the “Q system”, a novel methodology was introduced to derive QA and QB values related to scenarios involving external exposure from a distant source. These values are key parameters that respectively represent the total effective dose and total equivalent dose to the skin, from all primary and secondary particles contributing to radiation exposure. The International Working Group (WG A1/A2) is established and associated with the TRANSSC Technical Expert Group on Radiation Protection (TTEG-RP). A review of the A1 and A2 values is performed in response to identified limitations within the existing Q system. The followed approach is based on Monte Carlo simulations that enabled the development of transfer functions aimed at reducing computational time and increasing the flexibility of dose evaluations for any radionuclide with known particle emission spectra. This method allows updating the QA and QB values to account for future data evolutions (decay data, fluence-to-dose conversion coefficients) and standardizing the calculation of regulation limits across all referenced radionuclides and scenarios related to external exposure. The transfer functions are established using three Monte Carlo simulation codes — FLUKA, Geant4, and MCNP — and address the previous limitations of the “Q system”, reflecting the latest ICRP recommendations and improvements in calculation techniques. The results of the WG show consistent agreement across the codes, with minor discrepancies observed at low primary energies due to statistical uncertainties and different handling of stopping power for electrons/positrons in the codes. This revised approach aligns with current standards and recommendations, ensuring that the radiological consequences of transport accidents are acceptable for the new A1 and A2 limits from a radiological protection perspective.

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Calculation and benchmark of fluence-to-local skin equivalent dose coefficients for neutrons with FLUKA, MCNP, and GEANT4 Monte-Carlo codes

Cited by 13 publications

References 13 publications

Skin dose contamination conversion coefficients. Benchmark with three simulation codes

Skin dose contamination conversion coefficients. Benchmark with three simulation codes

Relationship Between NM Data and Radiation Dose at Aviation Altitudes During GLE Events

Transfer functions for Q_A /Q_B international regulatory limits for the safe transport of radioactive materials

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Calculation and benchmark of fluence-to-local skin equivalent dose coefficients for neutrons with FLUKA, MCNP, and GEANT4 Monte-Carlo codes

Cited by 13 publications

References 13 publications

Skin dose contamination conversion coefficients. Benchmark with three simulation codes

Skin dose contamination conversion coefficients. Benchmark with three simulation codes

Relationship Between NM Data and Radiation Dose at Aviation Altitudes During GLE Events

Transfer functions for QA /QB international regulatory limits for the safe transport of radioactive materials

Contact Info

Product

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Transfer functions for Q_A /Q_B international regulatory limits for the safe transport of radioactive materials