Benchmarking Monte Carlo codes for the modelling of low-energy neutron production target reactions

MacLeod, S; Jakubowski, K; Vohradsky, J; Franklin, DR; Sakabe, T; Hamato, A; Okamura, M; Guatelli, S; Safavi-Naeini, M

Benchmarking Monte Carlo codes for the modelling of low-energy neutron production target reactions

MacLeod, S Jakubowski, K Vohradsky, J Franklin, DR Sakabe, T Hamato, A Okamura, M Guatelli, S Safavi-Naeini, M

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Publisher:: Elsevier
Publication Type:: Journal Article
Citation:: Computer Physics Communications, 2025, pp. 109998
Issue Date:: 2025-12

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Field	Value	Language
dc.contributor.author	MacLeod, S
dc.contributor.author	Jakubowski, K
dc.contributor.author	Vohradsky, J
dc.contributor.author	Franklin, DR
dc.contributor.author	Sakabe, T
dc.contributor.author	Hamato, A
dc.contributor.author	Okamura, M
dc.contributor.author	Guatelli, S
dc.contributor.author	Safavi-Naeini, M
dc.date.accessioned	2025-12-29T07:32:17Z
dc.date.available	2025-12-29T07:32:17Z
dc.date.issued	2025-12
dc.identifier.citation	Computer Physics Communications, 2025, pp. 109998
dc.identifier.issn	0010-4655
dc.identifier.uri	http://hdl.handle.net/10453/191161
dc.description.abstract	The increasing adoption of accelerator-based neutron sources (ABNS) for applications including neutron capture therapy (NCT) research has highlighted the need for accurate simulation tools. Precise modelling of the neutron production target is crucial to ensure that simulated predictions of neutron beam characteristics used for subsequent beam shaping assembly design are reliable. This work presents a comprehensive benchmarking of four widely-used Monte Carlo codes - Geant4, PHITS, FLUKA (CERN), and MCNP - for modelling low-energy neutron production target reactions. Using their recommended physics models and cross-section libraries, we evaluate each code’s performance in simulating four beam-target reactions: 7Li(p,n)7Be, 9Be(p,n)9B, 9Be(d,n)10B, and C(d,n)N. Predictions of neutron yield, angular distributions, and energy spectra are compared against available thick target experimental data. Results show varying levels of agreement between the codes depending on the reaction type, energy range, and beam characteristics. Geant4, MCNP and PHITS are the overall best performing codes for the simulation of total neutron yield and yield in the forward direction across most reactions. Across energies where experimental benchmarks exist, inter-code discrepancies in total and forward-directed yield are typically 10 to 30%, with larger deviations at near-threshold incident ion energies. PHITS provides the best overall reproduction of experimental spectra, particularly for the 9Be(p,n)9B reaction. Additionally, PHITS demonstrates superior computational performance for most reactions. These findings provide valuable guidance for ABNS design, highlighting the strengths and limitations of each code for the simulation of low-energy neutron production reactions.
dc.language	en
dc.publisher	Elsevier
dc.relation.ispartof	Computer Physics Communications
dc.relation.isbasedon	10.1016/j.cpc.2025.109998
dc.rights	info:eu-repo/semantics/openAccess
dc.subject	01 Mathematical Sciences, 02 Physical Sciences, 08 Information and Computing Sciences
dc.subject.classification	Nuclear & Particles Physics
dc.subject.classification	46 Information and computing sciences
dc.subject.classification	49 Mathematical sciences
dc.subject.classification	51 Physical sciences
dc.title	Benchmarking Monte Carlo codes for the modelling of low-energy neutron production target reactions
dc.type	Journal Article
utslib.for	01 Mathematical Sciences
utslib.for	02 Physical Sciences
utslib.for	08 Information and Computing Sciences
pubs.organisational-group	University of Technology Sydney
pubs.organisational-group	University of Technology Sydney/Faculty of Engineering and Information Technology
pubs.organisational-group	University of Technology Sydney/Faculty of Engineering and Information Technology/School of Electrical and Data Engineering
utslib.copyright.status	open_access	*
dc.rights.license	This work is licensed under a Creative Commons Attribution 4.0 International License (CC BY 4.0). To view a copy of this license, visit https://creativecommons.org/licenses/by/4.0/
dc.date.updated	2025-12-29T07:32:13Z
pubs.publication-status	Published

Abstract:

The increasing adoption of accelerator-based neutron sources (ABNS) for applications including neutron capture therapy (NCT) research has highlighted the need for accurate simulation tools. Precise modelling of the neutron production target is crucial to ensure that simulated predictions of neutron beam characteristics used for subsequent beam shaping assembly design are reliable. This work presents a comprehensive benchmarking of four widely-used Monte Carlo codes - Geant4, PHITS, FLUKA (CERN), and MCNP - for modelling low-energy neutron production target reactions. Using their recommended physics models and cross-section libraries, we evaluate each code’s performance in simulating four beam-target reactions: 7Li(p,n)7Be, 9Be(p,n)9B, 9Be(d,n)10B, and C(d,n)N. Predictions of neutron yield, angular distributions, and energy spectra are compared against available thick target experimental data. Results show varying levels of agreement between the codes depending on the reaction type, energy range, and beam characteristics. Geant4, MCNP and PHITS are the overall best performing codes for the simulation of total neutron yield and yield in the forward direction across most reactions. Across energies where experimental benchmarks exist, inter-code discrepancies in total and forward-directed yield are typically 10 to 30%, with larger deviations at near-threshold incident ion energies. PHITS provides the best overall reproduction of experimental spectra, particularly for the 9Be(p,n)9B reaction. Additionally, PHITS demonstrates superior computational performance for most reactions. These findings provide valuable guidance for ABNS design, highlighting the strengths and limitations of each code for the simulation of low-energy neutron production reactions.

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http://hdl.handle.net/10453/191161