Benchmarking OLTARIS For Deep Space Dose Analyses Using MCNP6
, 2015 OLTARIS, the On-Line Tool for the Assessment of Radiation In Space, is a one-dimensional nuclear transport code developed and utilized by NASA scientists to “study the effects of space radiation on shielding materials, electronics, and biological systems.
Baunach, John Daniel
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Supermirror physics with event biasing in MCNP6
, 2020 Beamlines for cold and thermal neutrons instruments use low-roughness multilayered films called supermirrors, which aim to reflect neutrons below a critical angle.
Bergmann, Ryan M. (author) +1 more
core +1 more source
SU-E-T-521: Investigation of the Uncertainties Involved in Secondary Neutron/gamma Production in Geant4/MCNP6 Monte Carlo Codes for Proton Therapy Application [PDF]
, 2015 A major concern in proton therapy is the production of secondary neutrons causing secondary cancers, especially in young adults and children. Most utilized Monte Carlo codes in proton therapy are Geant4 and MCNP.
GIUSTI, VALERIO +2 more
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Mcnp6 Code Development for One Dimensional Position Sensitive Thermal Neutron Detectors [PDF]
, 2018 The development of position sensitive thermal neutron detectors (PSD’s) began soon after the initial development of early model thermal neutron detectors.
Fustero, Joseph G
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Fission Multiplicity Distribution Sampling in MCNP6 Criticality Calculations [PDF]
, 2016 In the solution of the neutron transport equation, the k-effective eigenvalue is related to the average number of neutrons emitted in fission of the system. It can be shown that if the average number of neutrons emitted in fission and the average neutron
Ortega, Mario Ivan
core
Nuclear Science and Technology Open ResearchBackground Correlated sampling can be applied with batch statistics using MCNP6’s tally fluctuation chart (TFC) to reduce the uncertainty of a difference of tallies between a base case and a perturbed case without modifying the source code. The cases are
Jeffrey A. Favorite
doaj +1 more source
Design of a delayed neutron detection system for the ASTRID Sodium-cooled fast reactor
EPJ Web of Conferences, 2018 Delayed neutron detection systems are key apparati in Sodium cooled Fast Reactors to prevent safety accidents. Based on the feedbacks from Phenix and Superphenix, DND systems are studied by means of the Monte-Carlo particles transport code MCNP6 ...
Coulon Romain +5 more
doaj +1 more source
The fast neutron fluence and the activation monitor activity calculations using fine multigroup and continuous nuclear data [PDF]
EPJ Web of ConferencesThe fast neutron fluence and the activation monitor activities are routinely calculated with TORT deterministic code and BUGLE-B7 nuclear data library with 47 broad energy groups.
Lovecký Martin +2 more
doaj +1 more source
Enhanced Electron-Photon Transport in MCNP6
, 2014 Recently a variety of improved and enhanced methods for low-energy photon/electron transport have been developed for the Monte Carlo particle transport code MCNP6.
H. Grady Hughes
core +1 more source
Intercomparison of full energy peak efficiency curves for an HPGe detector using MCNP6 and GEANT4 [PDF]
, 2019 [EN] This work is focused on studying the capabilities of different Monte Carlo tools to complement the Full Energy Peak Efficiency (FEPE) calibration procedures of the Environmental Radioactivity Laboratory of the Universitat Politècnica de València ...
Sáez-Muñoz, Marina +4 more
core +1 more source