Calculation of Neutron Production Rates and Spectra from Compounds of Actinides and Light Elements

Vlaskin, G. N.; Khomiakov, Yuriy

doi:10.1051/epjconf/201715307033

Cited by 8 publications

(2 citation statements)

References 21 publications

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“…Various comparisons between the different codes and with experimental data are found in [6,[30][31][32]. In the following lines, we describe the results obtained with Geant4, that extend the comparisons performed in [31] and [6].…”

Section: Comparison With Other Codes and Validation With Experimental...mentioning

confidence: 62%

Neutron production induced by α-decay with Geant4

Mendoza

Cano‐Ott

Romojaro

et al. 2020

Nuclear Instruments and Methods in Physics Research Section A:

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Neutron production induced by (α,n) reactions is important in various scenarios.One of the most relevant ones is related to underground dark matter experiments, where the neutrons produced by the α-decay from radioactive contaminants in the detector materials can generate an irreducible background, limiting the sensitivity of the experiment. A precise estimate of the background due to these neutrons is crucial for the experiments currently taking data and for the design of the next generation detectors. In this work, we prove that Geant4 can be used to calculate neutron yields and energy spectra induced by α-decay. These neutrons are produced according to the information compiled in data libraries originally written in the ENDF-6 format. In this article we also review the different databases available, showing the differences and similarities among them. Finally, we compare several Geant4 neutron production yields and spectra with experimental data and other codes.

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Section: Comparison With Other Codes and Validation With Experimental...mentioning

confidence: 62%

Neutron production induced by α-decay with Geant4

Mendoza

Cano‐Ott

Romojaro

et al. 2020

Nuclear Instruments and Methods in Physics Research Section A:

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“…It should be noted that, apart from ORIGEN-S, there are other neutron source codes, e.g., SOURCES-4С (Wilson et al 2009), NEDIS-2m (Vlaskin and Khomyakov 2017), CHARS (Leniau and Wilson 2014), and others (Spirin et al 2015, Vlaskin and Khomyakov 2017). These codes fully focus on the neutron yield and spectrum calculation; the most commonly used code is SOURCES-4С, as the NEDIS-2m code (Vlaskin et al 2015, Spirin et al 2015, Vlaskin and Khomyakov 2017 is the one best adapted to problems of present-day nuclear power.…”

Section: Introductionmentioning

confidence: 99%

Peculiarities of the radiation formation in dispersed microencapsulated nuclear fuel

Bedenko¹,

Knyshev²,

Kuznetsova³

et al. 2019

NUCET

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A computational study has been performed for various options of the thorium reactor core loading. Neutronic studies of fuel have been conducted, its isotopic composition has been calculated, and the alpha emitters and the sources of neutron and photon radiation in the microencapsulated nuclear fuel have been analyzed. The studies had the purpose of developing the methodology used to estimate the radiation characteristics of nuclear fuel with a complex inner structure. Emphasis is placed on calculating the quantitative and spectral composition of the neutrons formed as the result of (a, n) reactions on small- and average-mass nuclei. The ratio of the quantity of the neutrons resulting from the (a, n) reactions to the quantity of the neutrons formed as the result of spontaneous fission has been calculated for fuel with heterogeneous and homogeneous arrangements of fissionable and structural elements. The developed tools will make it possible to estimate the neutron radiation dose, to revise the traditional fresh and spent fuel handling procedures, and to estimate, using the Rossi alpha method, the neutron multiplication factor in deeply subcritical systems. The neutron yield and spectrum were calculated using an analytical model and verified codes such as WIMS-D5B, ORIGEN-APP, SOURCES-4C and SRIM-2013.

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