Direct simulation method for estimating the concentration of nuclides undergoing transmutations

Article Nuclear Science & Technology

The probability distribution of transmutation events and its application for solving burnup problems

M. R. Omar et al.

Summary: This paper introduces a statistical model describing the selection of transmutation events at the nucleus level. It explores the probability distribution function of transmutation events experienced by nuclei and investigates the feasibility of using it to solve depletion problems. The results show that the proposed calculation can reproduce reference nuclides concentrations with acceptable accuracies.

PROGRESS IN NUCLEAR ENERGY (2022)

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Article Nuclear Science & Technology

Depletion capabilities in the OpenMC Monte Carlo particle transport code

Paul K. Romano et al.

Summary: An depletion solver has been implemented in OpenMC, which interfaces with the transport solver through a C++ API and uses various integration methods for advancing in time. The matrix exponential is evaluated using the incomplete partial fraction form of the Chebyshev rational approximation method. Simulations of a PWR pincell and a SFR assembly show that high-fidelity depletion chains lead to consistent predictions between OpenMC and Serpent.

ANNALS OF NUCLEAR ENERGY (2021)

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Article Nuclear Science & Technology

Development and validation of ISOBURN, a new depletion code

Ehsan Tavakkoli et al.

Summary: The new computer code ISOBURN has been developed to support both standalone and coupled-with-MCNP modes. This paper focuses on the features of ISOBURN in the standalone mode, including flux normalization method, self-adaptive time step adjustment algorithm, and consolidated depletion solver. The study shows that ISOBURN achieves remarkable computational savings with negligible accuracy loss.

ANNALS OF NUCLEAR ENERGY (2021)

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Article Nuclear Science & Technology