Research output: Contribution to report/book/conference proceedings › In-proceedings paper

**A novel computational platform for the propagation of nuclear data uncertainties through the fuel cycle code anicca.** / Hernandez Solis, Augusto; Merino Rodriguez, Ivan; Fiorito, Luca; Van den Eynde, Gert.

Research output: Contribution to report/book/conference proceedings › In-proceedings paper

Hernandez Solis, A, Merino Rodriguez, I, Fiorito, L & Van den Eynde, G 2020, A novel computational platform for the propagation of nuclear data uncertainties through the fuel cycle code anicca. in *PHYSOR 2020: Transition to a Scalable Nuclear Future.* Unknown, pp. 1-8, 2020 - PHYSOR, Cambridge, United Kingdom, 2020-03-29.

Hernandez Solis, A., Merino Rodriguez, I., Fiorito, L., & Van den Eynde, G. (2020). A novel computational platform for the propagation of nuclear data uncertainties through the fuel cycle code anicca. In *PHYSOR 2020: Transition to a Scalable Nuclear Future *(pp. 1-8). Unknown.

Hernandez Solis A, Merino Rodriguez I, Fiorito L, Van den Eynde G. A novel computational platform for the propagation of nuclear data uncertainties through the fuel cycle code anicca. In PHYSOR 2020: Transition to a Scalable Nuclear Future. Unknown. 2020. p. 1-8

@inproceedings{8dba73b018ae41d6889c809c8b83f2eb,

title = "A novel computational platform for the propagation of nuclear data uncertainties through the fuel cycle code anicca",

abstract = "This paper presents the first results of a computational platform dedicated to the propagation of nuclear data covariances, all the way to fuel cycle scenario observables. Such platform, based on in-house codes developed at SCK•CEN in Belgium, both for the creation of the many-randomized nuclear data libraries based on ENDF format and for fuel cycle scenario-studies (known as SANDY and ANICCA, respectively), was employed for the uncertainty assessment of the time-dependent inventory computed from a mono-recycling of Plutonium scenario based on a PWR fleet. An essential part of the procedure that deals with the creation of input data libraries to ANICCA, has been carried out this time by the SERPENT2 code. Due to the fact that its neutron transport and depletion parallelized calculation in 72 cores for up to 1640 days and 60 MWd/kg-HM takes almost one hour, it is feasible to finish a total of 100 ANICCA runs based on randomized input libraries created from ENDF/B-VII.1 neutron-reaction covariances in about one week. Therefore, it is consider that the computation of the output population statistics can be inferred from 100 observables representing time-dependent mass inventories. To mention a few results from the aforementioned NEA/OECD benchmark scenario, it was found out that the relative standard deviation of the accumulated plutonium in the final disposal after 120 years was of 7{\%}, while for curium it corresponded to 8{\%}. Thus, sources of uncertainty arising from neutron-reaction covariances do have an impact in the final quantitative analysis of the fuel cycle output uncertainties.",

keywords = "PHYSOR",

author = "{Hernandez Solis}, Augusto and {Merino Rodriguez}, Ivan and Luca Fiorito and {Van den Eynde}, Gert",

note = "Score=3",

year = "2020",

month = "3",

day = "29",

language = "English",

pages = "1--8",

booktitle = "PHYSOR 2020: Transition to a Scalable Nuclear Future",

publisher = "Unknown",

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T1 - A novel computational platform for the propagation of nuclear data uncertainties through the fuel cycle code anicca

AU - Hernandez Solis, Augusto

AU - Merino Rodriguez, Ivan

AU - Fiorito, Luca

AU - Van den Eynde, Gert

N1 - Score=3

PY - 2020/3/29

Y1 - 2020/3/29

N2 - This paper presents the first results of a computational platform dedicated to the propagation of nuclear data covariances, all the way to fuel cycle scenario observables. Such platform, based on in-house codes developed at SCK•CEN in Belgium, both for the creation of the many-randomized nuclear data libraries based on ENDF format and for fuel cycle scenario-studies (known as SANDY and ANICCA, respectively), was employed for the uncertainty assessment of the time-dependent inventory computed from a mono-recycling of Plutonium scenario based on a PWR fleet. An essential part of the procedure that deals with the creation of input data libraries to ANICCA, has been carried out this time by the SERPENT2 code. Due to the fact that its neutron transport and depletion parallelized calculation in 72 cores for up to 1640 days and 60 MWd/kg-HM takes almost one hour, it is feasible to finish a total of 100 ANICCA runs based on randomized input libraries created from ENDF/B-VII.1 neutron-reaction covariances in about one week. Therefore, it is consider that the computation of the output population statistics can be inferred from 100 observables representing time-dependent mass inventories. To mention a few results from the aforementioned NEA/OECD benchmark scenario, it was found out that the relative standard deviation of the accumulated plutonium in the final disposal after 120 years was of 7%, while for curium it corresponded to 8%. Thus, sources of uncertainty arising from neutron-reaction covariances do have an impact in the final quantitative analysis of the fuel cycle output uncertainties.

AB - This paper presents the first results of a computational platform dedicated to the propagation of nuclear data covariances, all the way to fuel cycle scenario observables. Such platform, based on in-house codes developed at SCK•CEN in Belgium, both for the creation of the many-randomized nuclear data libraries based on ENDF format and for fuel cycle scenario-studies (known as SANDY and ANICCA, respectively), was employed for the uncertainty assessment of the time-dependent inventory computed from a mono-recycling of Plutonium scenario based on a PWR fleet. An essential part of the procedure that deals with the creation of input data libraries to ANICCA, has been carried out this time by the SERPENT2 code. Due to the fact that its neutron transport and depletion parallelized calculation in 72 cores for up to 1640 days and 60 MWd/kg-HM takes almost one hour, it is feasible to finish a total of 100 ANICCA runs based on randomized input libraries created from ENDF/B-VII.1 neutron-reaction covariances in about one week. Therefore, it is consider that the computation of the output population statistics can be inferred from 100 observables representing time-dependent mass inventories. To mention a few results from the aforementioned NEA/OECD benchmark scenario, it was found out that the relative standard deviation of the accumulated plutonium in the final disposal after 120 years was of 7%, while for curium it corresponded to 8%. Thus, sources of uncertainty arising from neutron-reaction covariances do have an impact in the final quantitative analysis of the fuel cycle output uncertainties.

KW - PHYSOR

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/37234070

M3 - In-proceedings paper

SP - 1

EP - 8

BT - PHYSOR 2020: Transition to a Scalable Nuclear Future

PB - Unknown

ER -

ID: 6052894