Origami: A new interface for fuel assembly characterization with origen

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5 Scopus citations

Abstract

The new ORIGAMI interface to the well-established ORIGEN code for nuclear fuel depletion affords new capabilities useful for modeling the depletion of used nuclear fuel assemblies. Starting from a user-defined mesh composed of axial and/or radial burnup gradients, ORIGAMI calculates assembly characteristics through a series of point depletion calls to the ORIGEN sequence across the mesh, thereby effectively allowing a rapid 3-D assembly depletion calculation. Additionally, ORIGAMI provides a number of useful features for post-depletion analysis of used fuel assemblies, including visualization of selected nuclides and automated generation of materials inputs for further analysis in commonly-used formats like MCNP and KENO. The design of ORIGAMI is such to allow greatly simplified, high-fidelity analysis of the isotopie, thermal, and radiological characteristics of used nuclear fuel assemblies.

Original languageEnglish
Title of host publication15th International High-Level Radioactive Waste Management Conference 2015, IHLRWM 2015
PublisherAmerican Nuclear Society
Pages418-425
Number of pages8
ISBN (Electronic)9781510808102
StatePublished - 2015
Event15th International High-Level Radioactive Waste Management Conference, IHLRWM 2015 - Charleston, United States
Duration: Apr 12 2015Apr 16 2015

Publication series

Name15th International High-Level Radioactive Waste Management Conference 2015, IHLRWM 2015

Conference

Conference15th International High-Level Radioactive Waste Management Conference, IHLRWM 2015
Country/TerritoryUnited States
CityCharleston
Period04/12/1504/16/15

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