Photon transport physics in Serpent 2 Monte Carlo code

Kaltiaisenaho, Toni

doi:10.1016/j.cpc.2020.107143

Cited by 15 publications

(3 citation statements)

References 44 publications

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“…Due to the relatively low characteristic energy of the ray, the photoelectric effect dominates the interaction between the ray and the composites. The free path of the secondary particles generated by the photoelectric effect in the material medium is generally only in the micrometer scale, 21 which is lower than the particle size of ZnS:Ag phosphor in the glass matrix. Therefore, the glass phase is supposed to act as the host, and the energy deposited on the glass phase and then transferred to the phosphor contributes relatively small to the scintillating emission.…”

Section: Resultsmentioning

confidence: 99%

Glass‐ZnS:Ag scintillating composite for radiation detection

Tu,

Wang,

Liu

et al. 2024

J Am Ceram Soc.

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Neutrons are widely used in national defense, security, and medical health fields. It is critical to realize neutron detection with high efficiency. The most popular neutron detection scintillators such as lithium glass and 6LiF/ZnS:Ag screen exhibit insurmountable limitations: the former usually has relatively rather low light yield and latter is opaque. In this research, we report the successful construction of the novel full inorganic composite scintillators by low temperature co‐firing technology. The composite scintillator is derived from the ZnS:Ag and borate glass matrix, and it shows better transparency compared with the standard 6LiF/ZnS:Ag screen. It exhibits excellent scintillation properties with the X‐ray induced emission intensity of these composite scintillators reaching approximately 2.46 times of the standard Bi4Ge3O12 (BGO) crystal. The light output under thermal neutron excitation can reach 75 000 photons/neutron. In addition, it presents excellent neutron detection performance with natural abundance of 10B isotope. Our research findings can serve as a valuable reference for the advancement of robust neutron detection materials, particularly in the domain of ZnS:Ag‐based full inorganic scintillator for neutron detection.

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Section: Resultsmentioning

confidence: 99%

Glass‐ZnS:Ag scintillating composite for radiation detection

Tu,

Wang,

Liu

et al. 2024

J Am Ceram Soc.

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“…EPDL is extensively used in Monte Carlo simulation. Several well-known particle transport codes, such as EGSnrc [20], FLUKA [21], [22], Geant4 [4]- [6], ITS [23], MCNP [24], PHITS [25] and Serpent [26], base the simulation of e + e − pair production on the cross sections tabulated in EPDL.…”

Section: Cross Sections In Particle Transportmentioning

confidence: 99%

Validation of e⁺e⁻Pair Production Total Cross Sections for Monte Carlo Particle Transport

Tulio

Begalli

Choi

et al. 2022

IEEE Trans. Nucl. Sci.

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“…Spectroscopic information from reactor core gamma rays provides information for several other important applications, including the estimation of radiation doses [17], spectral properties [18], and the validation of neutron transport codes [19][20][21] that offer combined neutron/photon transport. Fission product quantification, especially short-lived isotopes, is relevant for emergency preparedness and modeling accident scenarios [22].…”

Section: Introductionmentioning

confidence: 99%

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

Pakari,

Lucas,

Darby

et al. 2024

JNE

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Gamma-ray spectroscopy is an effective technique for radioactive material characterization, routine inventory verification, nuclear safeguards, health physics, and source search scenarios. Gamma-ray spectrometers typically cannot be operated in the immediate vicinity of nuclear reactors due to their high flux fields and their resulting inability to resolve individual pulses. Low-power reactor facilities offer the possibility to study reactor gamma-ray fields, a domain of experiments hitherto poorly explored. In this work, we present gamma-ray spectroscopy experiments performed with various detectors in two reactors: The EPFL zero-power research reactor CROCUS, and the neutron beam facility at the Ohio State University Research Reactor (OSURR). We employed inorganic scintillators (CeBr3), organic scintillators (trans-stilbene and organic glass), and high-purity germanium semiconductors (HPGe) to cover a range of typical—and new—instruments used in gamma-ray spectroscopy. The aim of this study is to provide a guideline for reactor users regarding detector performance, observed responses, and therefore available information in the reactor photon fields up to 2 MeV. The results indicate several future prospects, such as the online (at criticality) monitoring of fission products (like Xe, I, and La), dual-particle sensitive experiments, and code validation opportunities.

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Photon transport physics in Serpent 2 Monte Carlo code

Cited by 15 publications

References 44 publications

Glass‐ZnS:Ag scintillating composite for radiation detection

Glass‐ZnS:Ag scintillating composite for radiation detection

Validation of e⁺e⁻Pair Production Total Cross Sections for Monte Carlo Particle Transport

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

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Photon transport physics in Serpent 2 Monte Carlo code

Cited by 15 publications

References 44 publications

Glass‐ZnS:Ag scintillating composite for radiation detection

Glass‐ZnS:Ag scintillating composite for radiation detection

Validation of e+e−Pair Production Total Cross Sections for Monte Carlo Particle Transport

Gamma-ray Spectroscopy in Low-Power Nuclear Research Reactors

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Product

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Validation of e⁺e⁻Pair Production Total Cross Sections for Monte Carlo Particle Transport