Phenomenological calculations of shielding spallation neutron sources

Fragopoulou, M.; Zamani, M.

doi:10.1016/j.nima.2013.02.023

Cited by 5 publications

(5 citation statements)

References 17 publications

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“…Consequently, this research verifies previous findings that iron has excellent shielding capabilities for fast neutrons, not only for 14 meV neutron energy distribution and high proton energy distribution but also for 200 MeV neutron energy. The absorption cross-section significantly affects the neutron energy below 1 eV; therefore, polyethylene material is the best option for low neutron shielding material [12,17,24]. However, there are better choices than polyethylene for fast neutrons.…”

Section: Resultsmentioning

confidence: 99%

“…Safety and radiation protection aspects require important knowledge of the materials for neutron radiation shielding. In addition, the radiation shielding cost influences a significant portion of the entire cost of building facilities [11,12]. Shielding designers need material data, such as flux, mass attenuation or removal cross-section, effective dose, and reduction factor, during preconstruction.…”

Section: Introductionmentioning

confidence: 99%

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Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Aliyah

Rahman

Radzi

et al. 2023

SPEKTRA

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Neutron encounters difficulties in shielding protection. Thus, many researchers have performed simulation and experimental research on neutron shielding materials. The characteristic of materials is highly dependent on neutron energy. The evaluation of neutron shielding for various materials, such as iron, concrete, aluminum, and borated polyethylene (BPE), was conducted in this paper through simulation using a Monte Carlo code of PHITS 3.27 and calculation via partial density method. A mono-energetic neutron source with an energy of 200 MeV is emitted perpendicular to the shielding material with a thickness of 105 cm. The parameters measured in this analysis include flux, fast neutron removal cross-section, neutron depth dose, ambient dose H*(10) equivalent, and neutron dose reduction factor (RF). Results show that iron is a good material against high-energy neutron and secondary photon radiation at the energy range with the highest removal cross-section and the lowest RF value (0.39), followed by concrete, BPE, and aluminum. The integrated fluence and effective dose profiles were consistent with previous results in the literature. Benchmarking calculation of neutron dose RF was conducted with other publications and was in good agreement within the value range.

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Section: Resultsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Aliyah

Rahman

Radzi

et al. 2023

SPEKTRA

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“…As a first step, the interaction length of neutrons for each neutron energy and shielding material was estimated. The determination of the interaction length was made using the relationship between the interaction length, λ, and inelastic cross section σ in [10,17] λ σ…”

Section: Calculationsmentioning

confidence: 99%

“…Considered the lethargy of neutrons and their mean free path, the neutron spectrum behind a shielding can be estimated using Eq. 1 [17]. In order to calculate the neutron spectrum behind a shielding material the neutron spectrum produced by the spallation sources was taken from the calculations made using DCM/DEM [20] and MCNPX codes [21].…”

Section: Calculationsmentioning

confidence: 99%

Radiation protection strategies in the environment of a spallation neutron source

Fragopoulou¹,

Zamani²

2018

Nucl Med Biomed Imaging

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Due to the high level of radiation generated by a spallation source, the construction of an effective shielding is necessary for radiation protection purposes. Neutron dose measurements and calculations around spallation sources are of great importance for an appropriate shielding study. Calculations of the spallation neutron attenuation by various shielding materials using a phenomenological model are presented. The calculations were compared with measurements using Solid State Nuclear Track (SSNTDs) as particle and fission detectors.

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“…In the past, a variety of measurements have been carried out for benchmarking purposes [15][16][17][18][19][20]. These measurements however have largely focused on iron/concrete shields or more complex shielding scenarios with the incident neutron energies ranging over the entire spallation source energy spectrum.…”

Section: Introductionmentioning

confidence: 99%

High-energy in-beam neutron measurements of metal-based shielding for accelerator-driven spallation neutron sources

DiJulio

Cooper-Jensen

Björgvinsdottir

et al. 2016

Phys. Rev. Accel. Beams

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Metal-based shielding plays an important role in the attenuation of harmful and unwanted radiation at an accelerator-driven spallation neutron source. At the European Spallation Source, currently under construction in Lund, Sweden, metal-based materials are planned to be used extensively as neutron guide substrates in addition to other shielding structures around neutron guides. The usage of metal-based materials in the vicinity of neutron guides however requires careful consideration in order to minimize potential background effects in a neutron instrument at the facility. Therefore, we have carried out a combined study involving high-energy neutron measurements and Monte Carlo simulations of metal-based shielding, both to validate the simulation methodology and also to investigate the benefits and drawbacks of different metal-based solutions. The measurements were carried out at The Svedberg Laboratory in Uppsala, Sweden, using a 174.1 MeV neutron beam and various thicknesses of aluminum-, iron-, and copper-based shielding blocks. The results were compared to Geant4 simulations and revealed excellent agreement. Our combined study highlights the particular situations where one type of metal-based solution may be preferred over another.

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Phenomenological calculations of shielding spallation neutron sources

Cited by 5 publications

References 17 publications

Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Combined Method of Bulk Material Shielding Evaluation for 200 Mev High Energy Neutron Source Using Phits Modelling and Partial Density

Radiation protection strategies in the environment of a spallation neutron source

High-energy in-beam neutron measurements of metal-based shielding for accelerator-driven spallation neutron sources

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