TL;DR
PyNMC is an open-source Python framework that simulates neutron multiplicity counting by coupling transport, emission, and source estimation tools, validated against benchmarks and available on GitHub.
Contribution
It introduces a novel, open-source, Python-native simulation framework integrating multiple specialized tools for neutron multiplicity counting, validated against benchmarks.
Findings
Validated against ESARDA benchmarks with good agreement.
Accurately simulates ($ ext{α}$, n) source rates with modern data.
Framework is available as a Docker container on GitHub.
Abstract
Neutron multiplicity counting (NMC) underpins plutonium assay in nuclear safeguards, arms control, and disarmament verification, but existing simulation tools are essentially limited to MCNPX-PoliMi [1] (export-controlled, MCNP license required) and ONMS [2] (open-source but built on Geant4 with no scripting API); other codes (RMC, MCNP-PTA) are institute-internal. We present PyNMC, an open-source, Python-native NMC simulation framework that couples OpenMC for transport with FREYA for event-by-event correlated prompt-neutron emission and ALPHANSO for native (, n)-source estimates, together with collision-level time-tagged event recording and a Python shift-register post-processor cross-validated against ONMS. The framework is validated against the ESARDA Neutron Multiplicity Benchmark on bare Cf (c2-10, c2-100), the low-multiplication Pu metal case c3s (M = 1.12 from an…
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