Nuclear data uncertainty quantification for the nuclide inventory of a Calvert Cliffs spent fuel sample

Federico Grimaldi; Luca Fiorito; Pablo Romojaro; Augusto Hernandez Solis

Nuclear data uncertainty quantification for the nuclide inventory of a Calvert Cliffs spent fuel sample

Federico Grimaldi, Luca Fiorito, Pablo Romojaro, Augusto Hernandez Solis

Research output › peer-review

Abstract

The impact of nuclear data cross section uncertainties and covariance matrices on the nuclide vector of spent nuclear fuel was investigated. This exercise was carried out for the Calvert Cliffs fuel assembly D047 benchmark available in the SFCOMPO database. Sample P irradiated in rod MKP109 for four cycles up to a burnup of approximately 44 GWd/MTU was selected for the analysis. Nuclear data uncertainties were taken from the most recent libraries released by evaluation projects JEFF, ENDF/B and JENDL, and were propagated using the SANDY code via a stochastic sampling approach. This paper provides a quantification of the uncertainty on the concentration of several actinides and fission products relevant for spent fuel management. A comparison of the uncertainty predictions using different nuclear data libraries is also included.

Original language	English
Title of host publication	Proceedings International Conference on Physics of Reactors 2022 (PHYSOR 2022)
Publisher	American Nuclear Society
Pages	903-912
Number of pages	10
Edition	2022
State	Published - 23 Jun 2022
Event	2022 - PHYSOR - International Conference on Physics of Reactors: Making Virtual a Reality: Advancements in Reactor Physics to Leap Forward Reactor Operation and Deployment - Sheraton Pittsburgh Hotel, Pittsburgh, PA Duration: 15 May 2022 → 20 May 2022

Conference

Conference	2022 - PHYSOR - International Conference on Physics of Reactors
Country/Territory	United States
City	Pittsburgh, PA
Period	2022-05-15 → 2022-05-20

Access to Document

https://www.ans.org/pubs/proceedings/article-51075/License: Unspecified

Cite this

@inproceedings{4b9bdf9cabb041f7a815a0ea7ff84485,

title = "Nuclear data uncertainty quantification for the nuclide inventory of a Calvert Cliffs spent fuel sample",

abstract = "The impact of nuclear data cross section uncertainties and covariance matrices on the nuclide vector of spent nuclear fuel was investigated. This exercise was carried out for the Calvert Cliffs fuel assembly D047 benchmark available in the SFCOMPO database. Sample P irradiated in rod MKP109 for four cycles up to a burnup of approximately 44 GWd/MTU was selected for the analysis. Nuclear data uncertainties were taken from the most recent libraries released by evaluation projects JEFF, ENDF/B and JENDL, and were propagated using the SANDY code via a stochastic sampling approach. This paper provides a quantification of the uncertainty on the concentration of several actinides and fission products relevant for spent fuel management. A comparison of the uncertainty predictions using different nuclear data libraries is also included.",

keywords = "Spent nuclear fuel, Nuclear data, Uncertainty analysis, SANDY, Serpent",

author = "Federico Grimaldi and Luca Fiorito and Pablo Romojaro and {Hernandez Solis}, Augusto",

note = "Score=3; 2022 - PHYSOR - International Conference on Physics of Reactors : Making Virtual a Reality: Advancements in Reactor Physics to Leap Forward Reactor Operation and Deployment ; Conference date: 15-05-2022 Through 20-05-2022",

year = "2022",

month = jun,

day = "23",

language = "English",

pages = "903--912",

booktitle = "Proceedings International Conference on Physics of Reactors 2022 (PHYSOR 2022)",

publisher = "American Nuclear Society",

address = "United States",

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}

Grimaldi, F , Fiorito, L , Romojaro, P & Hernandez Solis, A 2022, Nuclear data uncertainty quantification for the nuclide inventory of a Calvert Cliffs spent fuel sample. in Proceedings International Conference on Physics of Reactors 2022 (PHYSOR 2022). 2022 edn, American Nuclear Society, pp. 903-912, 2022 - PHYSOR - International Conference on Physics of Reactors, Pittsburgh, PA, Pennsylvania, United States, 2022-05-15. <https://www.ans.org/pubs/proceedings/article-51075/>

TY - GEN

T1 - Nuclear data uncertainty quantification for the nuclide inventory of a Calvert Cliffs spent fuel sample

AU - Grimaldi, Federico

AU - Fiorito, Luca

AU - Romojaro, Pablo

AU - Hernandez Solis, Augusto

N1 - Score=3

PY - 2022/6/23

Y1 - 2022/6/23

N2 - The impact of nuclear data cross section uncertainties and covariance matrices on the nuclide vector of spent nuclear fuel was investigated. This exercise was carried out for the Calvert Cliffs fuel assembly D047 benchmark available in the SFCOMPO database. Sample P irradiated in rod MKP109 for four cycles up to a burnup of approximately 44 GWd/MTU was selected for the analysis. Nuclear data uncertainties were taken from the most recent libraries released by evaluation projects JEFF, ENDF/B and JENDL, and were propagated using the SANDY code via a stochastic sampling approach. This paper provides a quantification of the uncertainty on the concentration of several actinides and fission products relevant for spent fuel management. A comparison of the uncertainty predictions using different nuclear data libraries is also included.

AB - The impact of nuclear data cross section uncertainties and covariance matrices on the nuclide vector of spent nuclear fuel was investigated. This exercise was carried out for the Calvert Cliffs fuel assembly D047 benchmark available in the SFCOMPO database. Sample P irradiated in rod MKP109 for four cycles up to a burnup of approximately 44 GWd/MTU was selected for the analysis. Nuclear data uncertainties were taken from the most recent libraries released by evaluation projects JEFF, ENDF/B and JENDL, and were propagated using the SANDY code via a stochastic sampling approach. This paper provides a quantification of the uncertainty on the concentration of several actinides and fission products relevant for spent fuel management. A comparison of the uncertainty predictions using different nuclear data libraries is also included.

KW - Spent nuclear fuel

KW - Nuclear data

KW - Uncertainty analysis

KW - SANDY

KW - Serpent

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/49744197

M3 - In-proceedings paper

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BT - Proceedings International Conference on Physics of Reactors 2022 (PHYSOR 2022)

PB - American Nuclear Society

T2 - 2022 - PHYSOR - International Conference on Physics of Reactors

Y2 - 15 May 2022 through 20 May 2022

ER -