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