Integral nuclear data validation using experimental spent nuclear fuel compositions

Gauld, Ian C.; Williams, Mark L.; Michel-Sendis, Franco; Martinez, Jesus S.

doi:10.1016/j.net.2017.07.002

Title: Integral nuclear data validation using experimental spent nuclear fuel compositions

Full Record
Other Related Research

Abstract

Measurements of the isotopic contents of spent nuclear fuel provide experimental data that are a prerequisite for validating computer codes and nuclear data for many spent fuel applications. Under the auspices of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) and guidance of the Expert Group on Assay Data of Spent Nuclear Fuel of the NEA Working Party on Nuclear Criticality Safety, a new database of expanded spent fuel isotopic compositions has been compiled. The database, Spent Fuel Compositions (SFCOMPO) 2.0, includes measured data for more than 750 fuel samples acquired from 44 different reactors and representing eight different reactor technologies. Measurements for more than 90 isotopes are included. This new database provides data essential for establishing the reliability of code systems for inventory predictions, but it also has broader potential application to nuclear data evaluation. Furthermore, the database, together with adjoint based sensitivity and uncertainty tools for transmutation systems developed to quantify the importance of nuclear data on nuclide concentrations, are described.

Authors:

^[1]; Williams, Mark L. ^[1]; Michel-Sendis, Franco ^[2]; Martinez, Jesus S. ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
OECD Nuclear Energy Agency, Boulogne-Billancourt (France)

Publication Date:: Wed Jul 19 00:00:00 EDT 2017

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1400163

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Engineering and Technology

Additional Journal Information:: Journal Volume: 49; Journal Issue: 6; Journal ID: ISSN 1738-5733

Publisher:: Korean Nuclear Society

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Adjoint Depletion; Nuclear Data; SFCOMPO Database; Spent Fuel; Uncertainty Analysis

Citation Formats


                    Gauld, Ian C., Williams, Mark L., Michel-Sendis, Franco, and Martinez, Jesus S. Integral nuclear data validation using experimental spent nuclear fuel compositions.  United States: N. p., 2017. 
Web.  doi:10.1016/j.net.2017.07.002.

Copy to clipboard


                    Gauld, Ian C., Williams, Mark L., Michel-Sendis, Franco, & Martinez, Jesus S. Integral nuclear data validation using experimental spent nuclear fuel compositions.  United States.  https://doi.org/10.1016/j.net.2017.07.002

Copy to clipboard


                    Gauld, Ian C., Williams, Mark L., Michel-Sendis, Franco, and Martinez, Jesus S. Wed .  
"Integral nuclear data validation using experimental spent nuclear fuel compositions".  United States.  https://doi.org/10.1016/j.net.2017.07.002.  https://www.osti.gov/servlets/purl/1400163.

Copy to clipboard


                    
@article{osti_1400163,

  title        = {Integral nuclear data validation using experimental spent nuclear fuel compositions},

  author       = {Gauld, Ian C. and Williams, Mark L. and Michel-Sendis, Franco and Martinez, Jesus S.},

  abstractNote = {Measurements of the isotopic contents of spent nuclear fuel provide experimental data that are a prerequisite for validating computer codes and nuclear data for many spent fuel applications. Under the auspices of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) and guidance of the Expert Group on Assay Data of Spent Nuclear Fuel of the NEA Working Party on Nuclear Criticality Safety, a new database of expanded spent fuel isotopic compositions has been compiled. The database, Spent Fuel Compositions (SFCOMPO) 2.0, includes measured data for more than 750 fuel samples acquired from 44 different reactors and representing eight different reactor technologies. Measurements for more than 90 isotopes are included. This new database provides data essential for establishing the reliability of code systems for inventory predictions, but it also has broader potential application to nuclear data evaluation. Furthermore, the database, together with adjoint based sensitivity and uncertainty tools for transmutation systems developed to quantify the importance of nuclear data on nuclide concentrations, are described.},

  doi          = {10.1016/j.net.2017.07.002},

  journal      = {Nuclear Engineering and Technology},

  number       = 6,

  volume       = 49,

  place        = {United States},

  year         = {Wed Jul 19 00:00:00 EDT 2017},

  month        = {Wed Jul 19 00:00:00 EDT 2017}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1016/j.net.2017.07.002

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 7 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

Experiment Isotopic Data Compiled by the OECD/NEA Expert Group on Assay Data for Spent Nuclear Fuel

Conference Gauld, Ian C. ; Rugama, Yolanda

An essential component of computational modeling and simulation is the availability of well-qualified experimental benchmark data against which calculation systems can be validated and the bias and uncertainty associated with the codes and data can be evaluated. The validation process is extremely important for safety and licensing to demonstrate that adequate margins for uncertainty have been included in the calculations. For safety evaluations involving spent nuclear fuel, the isotopic compositions and resulting activities calculated using depletion and decay codes must be validated against experimental determinations of the spent fuel content. In this process the isotopic concentrations predicted by the codesmore »« less
SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data

Journal Article Michel-Sendis, F. ; Gauld, I. ; Martinez, J. S. ; ... - Annals of Nuclear Energy (Oxford)

SFCOMPO-2.0 is the new release of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) database of experimental assay measurements. These measurements are isotopic concentrations from destructive radiochemical analyses of spent nuclear fuel (SNF) samples. We supplement the measurements with design information for the fuel assembly and fuel rod from which each sample was taken, as well as with relevant information on operating conditions and characteristics of the host reactors. These data are necessary for modeling and simulation of the isotopic evolution of the fuel during irradiation. SFCOMPO-2.0 has been developed and is maintained by the OECDmore »« less
Cited by 42
https://doi.org/10.1016/j.anucene.2017.07.022

Full Text Available
SCALE Validation Experience Using an Expanded Isotopic Assay Database for Spent Nuclear Fuel

Conference Gauld, Ian C. ; Radulescu, Georgeta ; Ilas, Germina

The availability of measured isotopic assay data to validate computer code predictions of spent fuel compositions applied in burnup-credit criticality calculations is an essential component for bias and uncertainty determination in safety and licensing analyses. In recent years, as many countries move closer to implementing or expanding the use of burnup credit in criticality safety for licensing, there has been growing interest in acquiring additional high-quality assay data. The well-known open sources of assay data are viewed as potentially limiting for validating depletion calculations for burnup credit due to the relatively small number of isotopes measured (primarily actinides with relativelymore »« less
Activities of the OECD/NEA Expert Group on Assay Data for Spent Nuclear Fuel

Conference Gauld, Ian C. ; Rugama, Yolanda

Management of spent nuclear fuel is a key issue for many NEA member countries. In nuclear criticality safety, the decision of many countries to advance burnup credit as part of their licensing strategy has heightened recent interest in experimental data needed to validate computer codes used in burnup credit calculations. This paper discusses recent activities of an Expert Group on assay data, formed under the OECD/NEA/NSC/WPNCS (Working Party on Nuclear Criticality Safety) to help coordinate isotopic assay data activities and facilitate international collaboration between NEA member countries developing or implementing burnup credit methodologies. Recent activities of the Expert Group aremore »« less
SFCOMPO Database of Spent Nuclear Fuel Assay Data – the Next Frontier

Conference Ilas, Germina ; Gauld, Ian ; Ortego, Pedro ; ...

SFCOMPO is the world’s largest database for measured spent nuclear fuel assay data. An international effort coordinated by the Nuclear Energy Agency (NEA) resulted in a significant expansion of the database and its release online in 2017 as a downloadable application. The SFCOMPO Technical Review Group (TRG) was recently formed under the direction of NEA’s Nuclear Science Committee/Working Party on Nuclear Criticality Safety and was mandated to maintain and further coordinate the development of SFCOMPO. This TRG is currently focused on (1) critical evaluation of the experimental assay data by independent experts and (2) development of benchmarks and benchmark modelsmore »« less
https://doi.org/10.1051/epjconf/202124710019

Full Text Available

Similar Records