Characterization of spent PWR fuel for decay heat, neutron and gamma-ray emmission: code comparison

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

Standard

Characterization of spent PWR fuel for decay heat, neutron and gamma-ray emmission: code comparison. / Hernandez Solis, Augusto; Fiorito, Luca; Stankovskiy, Alexey; Zerovnik, Gasper.

International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2019). 2019. ed. ANS - American Nuclear Society, 2019. p. 2736-2745.

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

Harvard

Hernandez Solis, A, Fiorito, L, Stankovskiy, A & Zerovnik, G 2019, Characterization of spent PWR fuel for decay heat, neutron and gamma-ray emmission: code comparison. in International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2019). 2019 edn, ANS - American Nuclear Society, pp. 2736-2745.

APA

Hernandez Solis, A., Fiorito, L., Stankovskiy, A., & Zerovnik, G. (2019). Characterization of spent PWR fuel for decay heat, neutron and gamma-ray emmission: code comparison. In International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2019) (2019 ed., pp. 2736-2745). ANS - American Nuclear Society.

Vancouver

Hernandez Solis A, Fiorito L, Stankovskiy A, Zerovnik G. Characterization of spent PWR fuel for decay heat, neutron and gamma-ray emmission: code comparison. In International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2019). 2019 ed. ANS - American Nuclear Society. 2019. p. 2736-2745

Author

Hernandez Solis, Augusto ; Fiorito, Luca ; Stankovskiy, Alexey ; Zerovnik, Gasper. / Characterization of spent PWR fuel for decay heat, neutron and gamma-ray emmission: code comparison. International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2019). 2019. ed. ANS - American Nuclear Society, 2019. pp. 2736-2745

Bibtex - Download

@inproceedings{d36ce463ae1d44e0b5784014a82a98e4,
title = "Characterization of spent PWR fuel for decay heat, neutron and gamma-ray emmission: code comparison",
abstract = "Coupled neutron transport and fuel depletion codes were compared on a simplified reference case of a PWR fuel assembly with initial 235U enrichment of 4{\%} and burnup of 51 GWd/tHM. Two Monte Carlo (MC) codes, Serpent and ALEPH2, and two deterministic codes, SCALE and DRAGON, were considered. A part of the nuclide vector was compared for a cooling period of 5 years. Additionally, observables, measurable by non-destructive analysis methods, i.e. decay heat, neutron and -ray emission rates, were compared as a function of cooling time. The differences between the two MC codes are small, mostly within 1{\%}. The differences in results obtained by deterministic codes are larger, and for production of actinides heavier than plutonium they may reach 7{\%}. The decay heat predictions with Serpent, ALEPH2 and DRAGON agree within 1{\%} for cooling time period 1-1000 years, while the prediction with SCALE module Polaris deviates by around 2{\%} within that cooling time period.",
keywords = "ALEPH2, Depletion analysis, Spent Fuel, code benchmark",
author = "{Hernandez Solis}, Augusto and Luca Fiorito and Alexey Stankovskiy and Gasper Zerovnik",
note = "Score=3",
year = "2019",
month = "9",
day = "1",
language = "English",
pages = "2736--2745",
booktitle = "International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2019)",
publisher = "ANS - American Nuclear Society",
address = "United States",
edition = "2019",

}

RIS - Download

TY - GEN

T1 - Characterization of spent PWR fuel for decay heat, neutron and gamma-ray emmission: code comparison

AU - Hernandez Solis, Augusto

AU - Fiorito, Luca

AU - Stankovskiy, Alexey

AU - Zerovnik, Gasper

N1 - Score=3

PY - 2019/9/1

Y1 - 2019/9/1

N2 - Coupled neutron transport and fuel depletion codes were compared on a simplified reference case of a PWR fuel assembly with initial 235U enrichment of 4% and burnup of 51 GWd/tHM. Two Monte Carlo (MC) codes, Serpent and ALEPH2, and two deterministic codes, SCALE and DRAGON, were considered. A part of the nuclide vector was compared for a cooling period of 5 years. Additionally, observables, measurable by non-destructive analysis methods, i.e. decay heat, neutron and -ray emission rates, were compared as a function of cooling time. The differences between the two MC codes are small, mostly within 1%. The differences in results obtained by deterministic codes are larger, and for production of actinides heavier than plutonium they may reach 7%. The decay heat predictions with Serpent, ALEPH2 and DRAGON agree within 1% for cooling time period 1-1000 years, while the prediction with SCALE module Polaris deviates by around 2% within that cooling time period.

AB - Coupled neutron transport and fuel depletion codes were compared on a simplified reference case of a PWR fuel assembly with initial 235U enrichment of 4% and burnup of 51 GWd/tHM. Two Monte Carlo (MC) codes, Serpent and ALEPH2, and two deterministic codes, SCALE and DRAGON, were considered. A part of the nuclide vector was compared for a cooling period of 5 years. Additionally, observables, measurable by non-destructive analysis methods, i.e. decay heat, neutron and -ray emission rates, were compared as a function of cooling time. The differences between the two MC codes are small, mostly within 1%. The differences in results obtained by deterministic codes are larger, and for production of actinides heavier than plutonium they may reach 7%. The decay heat predictions with Serpent, ALEPH2 and DRAGON agree within 1% for cooling time period 1-1000 years, while the prediction with SCALE module Polaris deviates by around 2% within that cooling time period.

KW - ALEPH2

KW - Depletion analysis

KW - Spent Fuel

KW - code benchmark

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/35069579

M3 - In-proceedings paper

SP - 2736

EP - 2745

BT - International Conference on Mathematics Computational Methods and Reactor Physics (M&C 2019)

PB - ANS - American Nuclear Society

ER -

ID: 5495395