Adjoint Monte Carlo neutron transport using cross-section probability table representation

Diop, Cheikh M’Backé; Petit, Odile; Jouanne, C.; Coste–Delclaux, Mireille

doi:10.1016/j.anucene.2010.04.018

Cited by 4 publications

(2 citation statements)

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“…Despite these difficulties, adjoint Monte Carlo methods are still a subject of active research per se [20][21][22] and in view of providing efficient variance reduction strategies for forward methods [23][24][25]. Bearing in mind the possibility of introducing adjoint methods into Tripoli-4 R , the production Monte Carlo transport code developed at CEA [26], in this work we illustrate a comparison of different adjoint simulation models.…”

Section: Introductionmentioning

confidence: 99%

Comparison of Monte Carlo methods for adjoint neutron transport

et al. 2018

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Solving the adjoint linear transport equation by Monte Carlo methods can be convenient for applications emerging in radiation shielding, where the detector is typically small (in terms of probability of detecting a signal). In this work we compare a few stochastic models that can be used in order to formally solve the adjoint transport equation by simulating artificial particles called adjunctons: these models differ in the form of adjuncton cross sections, scattering laws and multiplicities. In view of testing the accuracy and the performances of these schemes, we have selected some benchmark configurations for continuous-energy transport in infinite media, where reference solutions can be established. The role of population control techniques, such as Russian roulette and splitting, is also carefully examined.

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Section: Introductionmentioning

confidence: 99%

Comparison of Monte Carlo methods for adjoint neutron transport

et al. 2018

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“…Two approaches are possible: either a backward neutron propagation technique [22] or a proper forward procedure [18]. Many Authors have tackled the problem, with various attempts to maintain the same sampling approach as the one used in the direct Monte Carlo simulation, although no physical interpretation of such procedures is usually given [21,22,23,24]. The procedure leads to the introduction of a concept of pseudo-particles, named adjunctons, which, through an appropriate transport process, are distributed as the adjoint function.…”

Section: Introductionmentioning

confidence: 99%

The adjoint neutron transport equation and the statistical approach for its solution

Saracco

Dulla²,

Ravetto³

2016

Eur. Phys. J. Plus

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The adjoint equation was introduced in the early days of neutron transport and its solution, the neutron importance, has ben used for several applications in neutronics. The work presents at first a critical review of the adjoint neutron transport equation. Afterwards, the adjont model is constructed for a reference physical situation, for which an analytical approach is viable, i.e. an infinite homogeneous scattering medium. This problem leads to an equation that is the adjoint of the slowing-down equation that is well-known in nuclear reactor physics. A general closed-form analytical solution to such adjoint equation is obtained by a procedure that can be used also to derive the classical Placzek functions. This solution constitutes a benchmark for any statistical or numerical approach to the adjoint equation. A sampling technique to evaluate the adjoint flux for the transport equation is then proposed and physically interpreted as a transport model for pseudo-particles. This can be done by introducing appropriate kernels describing the transfer of the pseudo-particles in phase space. This technique allows estimating the importance function by a standard Monte Carlo approach. The sampling scheme is validated by comparison with the analytical results previously obtained.

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