Analysis of isotopic assay data from the MALIBU program

Germina Ilas, Ian C. Gauld

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

7 Scopus citations

Abstract

Acquisition and analysis of experimental isotopic assay data are essential for validating computer code predictions of isotopic composition for spent nuclear fuel in order to establish the uncertainty and bias associated with code predictions. Recently available experimental data for uranium oxide spent fuel, acquired through the MALIBU international program, are analyzed in this paper. The analyzed measurements include extensive actinide and fission product data of importance to spent fuel safety applications, including burnup credit, decay heat, and radiation source terms. Analysis of the measurements was performed using the two-dimensional depletion module TRITON in the SCALE computer code system.

Original languageEnglish
Title of host publicationInternational Conference on the Physics of Reactors 2008, PHYSOR 08
PublisherPaul Scherrer Institut
Pages1744-1750
Number of pages7
ISBN (Print)9781617821219
StatePublished - 2008
EventInternational Conference on the Physics of Reactors 2008, PHYSOR 08 - Interlaken, Switzerland
Duration: Sep 14 2008Sep 19 2008

Publication series

NameInternational Conference on the Physics of Reactors 2008, PHYSOR 08
Volume3

Conference

ConferenceInternational Conference on the Physics of Reactors 2008, PHYSOR 08
Country/TerritorySwitzerland
CityInterlaken
Period09/14/0809/19/08

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