Development and validation of a cross-section interface for PARCS

Stålek, Mathias; Demazière, Christophe

doi:10.1016/j.anucene.2008.07.003

Cited by 16 publications

(4 citation statements)

References 2 publications

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“…• The cross-section values are approximated by adding some perturbation or correction terms to values calculated at or around the nominal point, see e.g. [9], [10], [8], [11]. In general, the correction terms are based on physical knowledge or some expansion techniques, such as the Taylor expansion.…”

Section: Overview Of Different Methods For the Reconstruction Of Neutmentioning

confidence: 99%

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Use cases of Tucker decomposition method for reconstruction of neutron macroscopic cross-sections

Luu

Guillo²,

Maday

et al. 2017

Annals of Nuclear Energy

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The neutron cross-sections are inputs for nuclear reactor core simulations, they depend on various physical parameters. Because of industrial constraint (e.g. calculation time), the cross-sections can not be calculated on the fly due to the huge number of them. Hence, a reconstruction (or interpolation) process is used in order to evaluate the cross-sections at every point required, from (as few as possible) pre-calculated points. With most classical methods (for example: multilinear interpolation which is used in the core code COCAGNE of EDF (Électricité De France)), high accuracy for the reconstruction often requires a lot of pre-calculated points. We propose to use the Tucker decomposition, a low-rank tensor approximation method, to deal with this problem. The Tucker decomposition allows us to capture the most important information (one parameter at a time) to reconstruct the cross-sections. This information is stored as basis functions (called tensor directional basis functions) and the coefficients of the decomposition instead of pre-calculated points. Full reconstruction is done at the core code level using these decompositions. In this paper, a simplified multivariate analysis technique (based on statistical analysis) is also proposed in order to demonstrate that we can improve the quality of the acquired information as well as the accuracy of our approach. Using the Tucker decomposition, we will show in proposed use cases that we can reduce significantly the number of pre-calculated points and the storage size (compared to the multilinear interpolations) while achieving high accuracy for the reconstruction, even on a larger domain of parameters.

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Section: Overview Of Different Methods For the Reconstruction Of Neutmentioning

confidence: 99%

“…for points on the right hand side of (7) (11) where N j is the number of points of the fine discretization in direction j and r max j is the maximal number of tensor directional basis functions in direction j, over all cross-sections.…”

Section: Cost Of the Tucker Decomposition Compared To The Multilinearmentioning

confidence: 99%

Use cases of Tucker decomposition method for reconstruction of neutron macroscopic cross-sections

Luu

Guillo²,

Maday

et al. 2017

Annals of Nuclear Energy

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“…The capabilities of PARCS in eigenvalues and critical boron level searches, as well as control rods movement modeling makes it an important tool for analyzing short-term (KINETIC) and longterm (DEPLETION) transients of light water nuclear reactor. Meanwhile PARCS is coupled with RELAP5 and the TH feedbacks are elegantly implemented (Stålek and Demazi ere, 2008).…”

Section: Introductionmentioning

confidence: 99%

SARCS cross section library generator: Part two: Fast and quasi transients evaluations

Hadad

Porhemmat

2015

Progress in Nuclear Energy

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“…the macroscopic depletion and the microscopic depletion models) [3,10,11]. In the macroscopic depletion model, since the macroscopic cross sections needed as one of the input data to carry out the core calculations are mainly tabulated, the computational load can be saved.…”

Section: Overview Of the Cross-section Modelmentioning

confidence: 99%

A macroscopic cross-section model for BWR pin-by-pin core analysis

Fujita

Endo

Yamamoto

2013

Journal of Nuclear Science and Technology

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A macroscopic cross-section model used in boiling water reactor (BWR) pin-by-pin core analysis is studied. In the pin-by-pin core calculation method, pin-cell averaged cross sections are calculated for many combinations of core state and depletion history variables and are tabulated prior to core calculations. Variations of cross sections in a core simulator are caused by two different phenomena (i.e. instantaneous and history effects). We treat them through the core state variables and the exposure-averaged core state variables, respectively. Furthermore, the cross-term effect among the core state and the depletion history variables is considered. In order to confirm the calculation accuracy and discuss the treatment of the cross-term effect, the k-infinity and the pin-by-pin fission rate distributions in a single fuel assembly geometry are compared. Some cross-term effects could be negligible since the impacts of them are sufficiently small. However, the cross-term effects among the control rod history (or the void history) and other variables have large impacts; thus, the consideration of them is crucial. The present macroscopic cross-section model, which considers such dominant cross-term effects, well reproduces the reference results and can be a candidate in practical applications for BWR pin-by-pin core analysis on the normal operations.

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Development and validation of a cross-section interface for PARCS

Cited by 16 publications

References 2 publications

Use cases of Tucker decomposition method for reconstruction of neutron macroscopic cross-sections

Use cases of Tucker decomposition method for reconstruction of neutron macroscopic cross-sections

SARCS cross section library generator: Part two: Fast and quasi transients evaluations

A macroscopic cross-section model for BWR pin-by-pin core analysis

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