Computing the Matrix Exponential in Burnup Calculations

Pusa, Maria; Leppänen, Jaakko

doi:10.13182/nse09-14

Cited by 176 publications

(55 citation statements)

References 16 publications

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“…The code has a number of features that considerably reduce computational effort requirements, such as the unified energy grid (Leppänen, 2009) and the use of Woodcock delta-tracking (Leppänen, 2010) of particles. Serpent also has a built-in fuel depletion solver (Pusa and Leppänen, 2010) however this capability was not used for the most part of this work.…”

Section: Computer Codesmentioning

confidence: 99%

A perturbation-based susbtep method for coupled depletion Monte-Carlo codes

Kotlyar

Aufiero

Shwageraus

et al. 2017

Annals of Nuclear Energy

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a b s t r a c tCoupled Monte Carlo (MC) methods are becoming widely used in reactor physics analysis and design. Many research groups therefore, developed their own coupled MC depletion codes. Typically, in such coupled code systems, neutron fluxes and cross sections are provided to the depletion module by solving a static neutron transport problem. These fluxes and cross sections are representative only of a specific time-point. In reality however, both quantities would change through the depletion time interval. Recently, Generalized Perturbation Theory (GPT) equivalent method that relies on collision history approach was implemented in Serpent MC code. This method was used here to calculate the sensitivity of each nuclide and reaction cross section due to the change in concentration of every isotope in the system. The coupling method proposed in this study also uses the substep approach, which incorporates these sensitivity coefficients to account for temporal changes in cross sections. As a result, a notable improvement in time dependent cross section behavior was obtained. The method was implemented in a wrapper script that couples Serpent with an external depletion solver. The performance of this method was compared with other existing methods. The results indicate that the proposed method requires substantially less MC transport solutions to achieve the same accuracy.Published by Elsevier Ltd.

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Section: Computer Codesmentioning

confidence: 99%

A perturbation-based susbtep method for coupled depletion Monte-Carlo codes

Kotlyar

Aufiero

Shwageraus

et al. 2017

Annals of Nuclear Energy

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“…It should be noted that even though this is a relatively new feature, built in burnup capability has been available in Serpent for years. An overview of the general methodology is provided in , and the depletion solver based on the Chebyshev Rational Approximation Method (CRAM) is introduced in Pusa and Leppänen (2010).…”

Section: Automated Burnup Sequencementioning

confidence: 99%

Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code

Leppänen

Pusa

Fridman

2016

Annals of Nuclear Energy

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“…The necessity for external coupling with other numerical tools for analyzing the nuclear reactor core was significantly reduced. The main competition to the TTA method implemented in MCB are the assorted variations of the exponential matrix method; e.g., the Chebyshev Rational Approximation Method (CRAM) implemented in SERPENT code [25]. All MCNP features are available in the MCB, and some new ones were added.…”

Section: Mcbmentioning

confidence: 99%

The MCB Code for Numerical Modeling of Fourth Generation Nuclear Reactors

Oettingen

Cetnar

Mirowski

2015

csci

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R&D in the nuclear reactor physics demands state-of-the-art numerical tools that are able to characterize investigated nuclear systems with high accuracy. In this paper, we present the Monte Carlo Continuous Energy Burnup Code (MCB) developed at AGH University's Department of Nuclear Energy. The code is a versatile numerical tool dedicated to simulations of radiation transport and radiation-induced changes in matter in advanced nuclear systems like Fourth Generation nuclear reactors.We present the general characteristics of the code and its application for modeling of Very-High-Temperature Reactors and Lead-Cooled Fast Rectors. Currently, the code is being implemented on the supercomputers of the Academic Computer Center (CYFRONET) of AGH University and will soon be available to the international scientific community.

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Computing the Matrix Exponential in Burnup Calculations

Cited by 176 publications

References 16 publications

A perturbation-based susbtep method for coupled depletion Monte-Carlo codes

A perturbation-based susbtep method for coupled depletion Monte-Carlo codes

Overview of methodology for spatial homogenization in the Serpent 2 Monte Carlo code

The MCB Code for Numerical Modeling of Fourth Generation Nuclear Reactors

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