Published 2015 | Version v1
Book

Multidimensional Cross section library interpolation for the Bright-lite reactor modeling software - 5304

  • 1. University of Texas Austin, Austin, TX (United States)

Description

The Bright-lite reactor modeling software is a medium fidelity tool that uses cross section libraries to generate burnup and isotopic composition vectors. Using these curves the software is capable of determining output compositions and burnups for a given input fuel composition. This dependence on cross section libraries limits the effectiveness of Bright-lite to specific reactor designs. To increase the accuracy of the tool past these specific libraries a multidimensional interpolation method is used to generate interpolated libraries. The interpolation method used is derived from the Shepard multidimensional interpolation method. This method was chosen because it does not require a grid-making structure for the libraries used to perform the interpolation. Additionally this method allows for interpolation over the entire n-dimensional space that a reactor design might be modeled with. This paper demonstrates the effectiveness of the interpolation method to interpolation between the libraries used by Bright-lite. A pre-generated set of libraries are used to interpolate on the parameters of burnup and enrichment. Interpolations will first be performed to show the interpolation method is capable of matching known libraries within the bounds of the interpolation. In addition, a test will be conducted to show the effectiveness of the interpolation method on systems of libraries that do not create a grid for bounding the parametric system. This technique will allow for the rapid simulation of several reactor models using unique burnup and enrichment characteristics. (authors)

Availability note (English)

Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France)
Part of:
GLOBAL 2015 Proceedings

Additional details

Publishing Information

Publisher
Societe Francaise d'Energie Nucleaire - SFEN
Imprint Place
Paris (France)
ISBN
978-1-4951-6286-2
Imprint Title
GLOBAL 2015 Proceedings
Imprint Pagination
2455 p.
Journal Page Range
p. 856-862

Conference

Title
GLOBAL 2015 - Nuclear fuel cycle for a low-carbon future
Dates
21-24 Sep 2015
Place
Paris (France)

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
49047607
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
B CODES; BURNUP; CHEMICAL COMPOSITION; COMPUTERIZED SIMULATION; SPENT FUELS; WATER COOLED REACTORS
Descriptors DEC
COMPUTER CODES; ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; SIMULATION

Optional Information

Notes
6 refs.