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Title: ARIADNE – a program estimating covariances in detail for neutron experiments

Journal Article · · EPJ Nuclear Sciences and Technologies
DOI:https://doi.org/10.1051/epjn/2018012· OSTI ID:1489949

The python program ARIADNE is a tool developed for evaluators to estimate detailed uncertainties and covariances for experimental data in a consistent and efficient manner. Currently, it is designed to aid in the uncertainty quantification of prompt fission neutron spectra, and was employed to estimate experimental covariances for CIELO and ENDF/B-VIII.0 evaluations. It provides a streamlined way to estimate detailed covariances by (1) implementing uncertainty quantification algorithms specific to the observables, (2) defining input quantities for typically encountered uncertainty sources and correlation shapes, and (3) automatically generating plots of data, uncertainties and correlations, GND formatted XML and plain text output files. Covariances of the same and between different datasets can be estimated, and tools are provided to assemble a database of experimental data and covariances for an evaluation based on ARIADNE outputs. The underlying IPython notebook files can be easily stored, including all assumptions on uncertainties, leading to more reproducible inputs for nuclear data evaluations. Here, the key inputs and outputs are shown along with a representative example for the current version of ARIADNE to illustrate its usability and to open a discussion on how it could address further needs of the nuclear data evaluation community.

Research Organization:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
89233218CNA000001; AC52-06NA25396
OSTI ID:
1489949
Report Number(s):
LA-UR-17-30469
Journal Information:
EPJ Nuclear Sciences and Technologies, Vol. 4; ISSN 2491-9292
Country of Publication:
United States
Language:
English

References (10)

Prompt Fission Neutron Spectra of Actinides journal January 2016
ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data journal February 2018
Template for estimating uncertainties of measured neutron-induced fission cross-sections journal January 2018
CIELO Collaboration Summary Results: International Evaluations of Neutron Reactions on Uranium, Plutonium, Iron, Oxygen and Hydrogen journal February 2018
The Need for Precise and Well-documented Experimental Data on Prompt Fission Neutron Spectra from Neutron-induced Fission of 239Pu journal January 2016
Evaluations of Energy Spectra of Neutrons Emitted Promptly in Neutron-induced Fission of 235 U and 239 Pu journal February 2018
Towards a More Complete and Accurate Experimental Nuclear Reaction Data Library (EXFOR): International Collaboration Between Nuclear Reaction Data Centres (NRDC) journal June 2014
Web Tool for Constructing a Covariance Matrix from EXFOR Uncertainties journal January 2012
Generalized Nuclear Data: A New Structure (with Supporting Infrastructure) for Handling Nuclear Data journal December 2012
Uranium and Plutonium Average Prompt-fission Neutron Energy Spectra (PFNS) from the Analysis of NTS NUEX Data journal May 2014

Figures / Tables (6)


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