Radiation Shielding

Shultis, J. Kenneth; Faw, R.E.

doi:10.1007/978-1-4614-5716-9_14

Cited by 44 publications

(92 citation statements)

References 34 publications

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“…This elemental analysis and its effects are in accordance with previous studies (Kaplan, 1989;Shultis and Faw, 1996). The probability of a photoelectric event has a strong dependence on atomic number of the material, which is a fine example of how water in some cases can be a better shielding material than lead (with the same number of mean free paths).…”

Section: Results For Gamma-ray Attenuationsupporting

confidence: 85%

Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications

Ipbüker

Nulk

Gulik

et al. 2015

Nuclear Engineering and Design

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Section: Results For Gamma-ray Attenuationsupporting

confidence: 85%

Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications

Ipbüker

Nulk

Gulik

et al. 2015

Nuclear Engineering and Design

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“…First, the proton energy for a given incident energy and cosine of center-of-mass (CM) neutron scattering angle must be calculated. For the generalized case of scatter on any stationary body, the energy of the recoil nucleus is given as (Shultis and Faw, 2000)…”

Section: Methodsmentioning

confidence: 99%

Response functions for computing absorbed dose to skeletal tissues from neutron irradiation

et al. 2011

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Spongiosa in the adult human skeleton consists of three tissues - active marrow (AM), inactive marrow (IM), and trabecularized mineral bone (TB). Active marrow is considered to be the target tissue for assessment of both long-term leukemia risk and acute marrow toxicity following radiation exposure. The total shallow marrow (TM50), defined as all tissues laying within the first 50 μm the bone surfaces, is considered to be the radiation target tissue of relevance for radiogenic bone cancer induction. For irradiation by sources external to the body, kerma to homogeneous spongiosa has been used as a surrogate for absorbed dose to both of these tissues, as direct dose calculations are not possible using computational phantoms with homogenized spongiosa. Recent microCT imaging of a 40-year-old male cadaver has allowed for the accurate modeling of the fine microscopic structure of spongiosa in many regions of the adult skeleton [Hough et al PMB (2011)]. This microstructure, along with associated masses and tissue compositions, was used to compute specific absorbed fractions (SAF) values for protons originating in axial and appendicular bone sites [Jokisch et al PMB (submitted)]. These proton SAFs, bone masses, tissue compositions, and proton production cross-sections, were subsequently used to construct neutron dose response functions (DRFs) for both AM and TM50 targets in each bone of the reference adult male. Kerma conditions were assumed for other resultant charged particles. For comparison, active marrow, total shallow marrow, and spongiosa kerma coefficients were also calculated. At low incident neutron energies, AM kerma coefficients for neutrons correlate well with values of the AM DRF, while total marrow (TM) kerma coefficients correlate well with values of the TM50 DRF. At high incident neutron energies, all kerma coefficients and DRFs tend to converge as charged particle equilibrium (CPE) is established across the bone site. In the range of 10 eV to 100 MeV, substantial differences are observed among the kerma coefficients and DRF. As a result, it is recommended that the AM kerma coefficient be used to estimate the AM DRF, and that the TM kerma coefficient be used to estimate the TM50 DRF below 10 eV. Between 10 eV and 100 MeV, the appropriate DRF should be used as presented in this study. Above 100 MeV, spongiosa kerma coefficients apply well for estimating skeletal tissue doses. DRF values for each bone site as a function of energy are provided in an electronic annex to this article.

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“…where E is the photon energy in MeV, and en / is given in Table C.5 of the same text (Shultis and Faw 2000). Using this response function in MCNP produces an f4 tally output in units of R (source photon) Ϫ1 .…”

Section: Tallies and Spectra Formationmentioning

confidence: 99%

“…The de card stores values for the photon energy, while the df card stores the corresponding values of the response function. The response function (eqn 5.30, Shultis and Faw 2000) that was implemented is given by the expression…”

Section: Tallies and Spectra Formationmentioning

confidence: 99%

Evaluation of Scattered Radiation in a Calibration Range Using Exposure Rate Energy Spectra

Petrie¹,

Blue²,

Herminghuysen

2012

Health Physics

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ISO standard 4037 specifies that for calibrating protection level dosimeters, scattered radiation should contribute less than 5% of the exposure. In previous work, the authors reported the results of an MCNP analysis of the shadow shield technique that was performed for a calibration range with a Cs irradiator. This paper examines the energy distribution of the photons contributing to the exposure percent scatter (S%) and the detailed origin of the scatter that originates in the irradiator. In summary, it reports that: 1) the majority of S% is due to photons with energies that are significantly below the source energy, 2) a significant percentage of S% is due to photons that scatter within the source and source capsule walls, and 3) S% due to scatter within the irradiator is even more significant than previously reported.

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Radiation Shielding

Cited by 44 publications

References 34 publications

Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications

Radiation shielding properties of a novel cement–basalt mixture for nuclear energy applications

Response functions for computing absorbed dose to skeletal tissues from neutron irradiation

Evaluation of Scattered Radiation in a Calibration Range Using Exposure Rate Energy Spectra

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