%0 Journal Article %T Comparison of Monte Carlo methods for adjoint neutron transport %+ CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire) (CEA-DES (ex-DEN)) %+ Service d’Études des Réacteurs et de Mathématiques Appliquées (SERMA) %+ Politecnico di Torino = Polytechnic of Turin (Polito) %A Vitali, V. %A Dulla, S. %A Ravetto, P. %A Zoia, A. %< avec comité de lecture %@ 2190-5444 %J The European Physical Journal Plus %I Springer %V 133 %N 8 %P 317 %8 2018 %D 2018 %R 10.1140/epjp/i2018-12132-9 %Z PACS. 28.41.Ak Theory, design, and computerized simulation – 02.50.Ng Distribution theory and Monte Carlo studies %Z Physics [physics]/Nuclear Experiment [nucl-ex] %Z Physics [physics]/Nuclear Theory [nucl-th]Journal articles %X Solving the adjoint linear transport equation by Monte Carlo methods can be convenient forapplications emerging in radiation shielding, where the detector is typically small (in terms of probabilityof detecting a signal). In this work we compare a few stochastic models that can be used in order toformally solve the adjoint transport equation by simulating artificial particles called adjunctons thesemodels dier in the form of adjuncton cross sections, scattering laws and multiplicities. In view of testingthe accuracy and the performances of these schemes, we have selected some benchmark configurations forcontinuous-energy transport in infinite media, where reference solutions can be established. The role ofpopulation control techniques, such as Russian roulette and splitting, is also carefully examined %G English %2 https://cea.hal.science/cea-02339764/document %2 https://cea.hal.science/cea-02339764/file/201800000762.pdf %L cea-02339764 %U https://cea.hal.science/cea-02339764 %~ CEA %~ DEN %~ CEA-UPSAY %~ UNIV-PARIS-SACLAY %~ CEA-UPSAY-SACLAY %~ DEN-SACLAY %~ GS-PHYSIQUE