WebbMonte Carlo N-Particle Transport ( MCNP) [2] is a general-purpose, continuous-energy, generalized-geometry, time-dependent, Monte Carlo radiation transport code designed to …
Neutron beam characterization and neutron yield for 9Be(p, n)9B …
Webb1 feb. 2024 · Comparison of PHITS2.88 and MCNP6.1 for the characterization of a LUPIN-II neutron area monitor. R. García-Baonza, Adrián Murcia-Morales, E. Gallego Physics Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine 2024 2 PDF View 1 excerpt Webb1 okt. 2024 · The LUPIN-II MCNP geometrical model reported and benchmarked in ( García-Baonza et al., 2024) has been used in this work to calculate the response function of this monitor with MCNP and PHITS, employing the following versions of the codes: MCNP6.1 and PHITS2.88. focaccia backform
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Webb13 apr. 2024 · The Computer Program Service organises training courses and workshops on the widely used computer programs. Additional training courses on nuclear data processing and thermodynamic data collection and assessment are organised by the NEA Data Bank. Upcoming events WebbA3.10 No. When stdcut is set, PHITS checks the statistical errors of all data in the tally. Thus, you have to limit the meshes only to the regions of your interest in the case of … Webb5 jan. 2024 · there are too many differences between the OpenMC input and MCNP input to be able to compare them. The concrete material description substantially differs between the two. OpenMC: 52.9% … focal 165krx2