Resonance and Thermal Neutron Self-Shielding in Cobalt Foils and Wires

Eastwood, T. A.; Werner, R.

doi:10.13182/nse62-a26181

Cited by 26 publications

(16 citation statements)

References 1 publication

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“…As shown in Figures 4 and 5, the result of present simulated G res factors for Gold and Cobalt foils has reasonable agreement with the experimental and calculated data by Gongalves [9], Brose [12] and Eastwood [2].…”

Section: Advanced Technologies and Applications Of Neutron Activationsupporting

confidence: 85%

“…The calculated resonance neutron self-shielding correction factors for Cobalt foils of different thickness, in comparison with published data by Gongalves[9] and Eastwood[2].…”

supporting

confidence: 52%

“…Lopes et al [1] calculated the values of epithermal neutron selfshielding factors, including isotopic scattering, for foil of Au-197 and Co-59. Eastwood et al [2] reported experimental values of resonance neutron self-shielding factors for foils and wires of Co-59, by the activation technique. Brose [3] measured the resonance neutron absorption factors for Gold foils with different thickness.…”

Section: Introductionmentioning

confidence: 99%

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Monte Carlo Simulation of Correction Factors for Neutron Activation Foils

Nguyen¹

2019

Advanced Technologies and Applications of Neutron Activation Analysis

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In the conventional neutron activation analysis, the elemental concentrations are normally determined from the comparison ratios between the measured specific activities of the sample and the standard reference material. An advantage in the comparison ratio method is that the systematic error due to neutron self-shielding and multi-scattering effects is canceled out, and the correction factors can be ignored but the preparation of reference standards to match the same conditions with those of various samples is the main difficulty. In the modern trend of neutron activation analysis, the K 0-standardization method has been developed and applied in almost all the NAA laboratories. An important research work in the procedure under this method is the characteristic information regarding the neutron source, such as thermal and epithermal neutron fluxes, and epithermal spectrum shape-factor. These neutron spectrum parameters are experimentally determined by using the activation foils, in which the corrections for all neutron effects cause systematic errors should be taken into account. Using the MCNP5 code, a wellknown Monte Carlo simulation program, the results of correction factors of thermal, epithermal and resonance neutron self-shielding factors for Au, Co, Mn, W activation foils are presented in this chapter.

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Section: Advanced Technologies and Applications Of Neutron Activationsupporting

confidence: 85%

“…The calculated resonance neutron self-shielding correction factors for Cobalt foils of different thickness, in comparison with published data by Gongalves[9] and Eastwood[2].…”

supporting

confidence: 52%

Section: Introductionmentioning

confidence: 99%

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Monte Carlo Simulation of Correction Factors for Neutron Activation Foils

Nguyen¹

2019

Advanced Technologies and Applications of Neutron Activation Analysis

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“…The gamma-ray count rates were measured using OR-TEC 70% HPGe detector; energy resolution about 4.1 keV at the 1332.5 keV γ-line of 60 Co. The data acquisition and analysis were performed using Genie 2000 Spectroscopy Software.…”

Section: Gamma Ray Measurementsmentioning

confidence: 99%

Mathematical formulae for neutron self-shielding properties of media in an isotropic neutron field

W.¹,

Elmaghraby²,

Salama³

et al. 2022

Preprint

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The complexity of the neutron transport phenomenon throws its shadows on every physical system wherever neutron is produced or used. In the current study, an ab initio derivation of the neutron self-shielding factor, the problem of the decrease of the neutron flux as it penetrates into a material placed in an isotropic neutron field, has been attempted employing the theory of steady-state neutron transport, starting from Stuart's formula. Simple formulae were derived based on the integral cross-section parameters, which can be adopted by the user according to various variables, such as the neutron flux distribution and geometry of the simulation at hand. The concluded formulae of the self-shielding factors comprise an inverted sigmoid function normalized a weight representing the ratio between the total and scattering macroscopic cross-sections of the medium. The general convex volume geometries are reduced to a set of chord lengths, while the neutron interactions probabilities within the volume are parameterized to the epithermal and thermal neutron energies. The arguments of the inverted-sigmoid function were derived from a simplified version of neutron transport formulation. Accordingly, the obtained general formulae were successful in giving the experimental values of the neutron self-shielding factor for different elements and different geometries. The results were validated by comparing them to the experimental data as well as a variety of data extracted from the literature.

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“…Typically, this type of overall effective self-shielding factor for a mixed neutron spectrum is composed from G th and its epithermal equivalent G epi and can be applied to bare target irradiation measurements [46]. Unfortunately, theoretical calculations for G epi are environment dependent and contain important alterations according to the current unknowns at the McClellan site [41,[48][49][50][51][52][53]. Therefore, our new empirical calibration approach aims to isolate and still calculate this overall effective self-shielding factor when detailed reactor parameter information is not available.…”

Section: Activation Analysismentioning

confidence: 99%

Preparation and Characterization of Thin Arsenic Targets for Stacked-Target Experiments

Voyles,

Fox,

Morrell

et al. 2021

Preprint

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Thin uniform arsenic targets suitable for high-fidelity cross section measurements in stacked-target experiments were prepared by electrodeposition of arsenic on titanium backings from aqueous solutions. Electrolytic cells were constructed and capable of arsenic deposits ranging in mass from approximately 1 to 29 mg (0.32-7.22 mg/cm 2 , 0.57-12.62 µm). Examination of electrodeposit surface morphology by scanning electron microscopy and microanalysis was performed to investigate the uniformity of produced targets. Brief studies of plating growth dynamics and structural properties through cyclic voltammetry were also undertaken. An alternative target fabrication approach by vapor deposition was additionally conducted. We further introduce a non-destructive characterization method for thin targets by neutron activation, which is independent of neutron flux shape, environmental factors, and source geometry, while correcting for any potential scatter or absorption effects.

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Resonance and Thermal Neutron Self-Shielding in Cobalt Foils and Wires

Cited by 26 publications

References 1 publication

Monte Carlo Simulation of Correction Factors for Neutron Activation Foils

Monte Carlo Simulation of Correction Factors for Neutron Activation Foils

Mathematical formulae for neutron self-shielding properties of media in an isotropic neutron field

Preparation and Characterization of Thin Arsenic Targets for Stacked-Target Experiments

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