Neutronic analyses of the FREYA experiments in support of the ALFRED lead-cooled fast reactor core design and licensing

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Neutronic analyses of the FREYA experiments in support of the ALFRED lead-cooled fast reactor core design and licensing. / Sarotto, Massimo; Firpo, Gabriele; Kochetkov, Anatoly; Krása, Antonin; Fridman, Emil; Cetnar, Jerzy.

In: Journal of Nuclear Engineering and Radiation Science, Vol. 6, No. NERS-18-1132, 011402, 05.01.2020, p. 1-12.

Research output: Contribution to journalArticlepeer-review

Harvard

Sarotto, M, Firpo, G, Kochetkov, A, Krása, A, Fridman, E & Cetnar, J 2020, 'Neutronic analyses of the FREYA experiments in support of the ALFRED lead-cooled fast reactor core design and licensing', Journal of Nuclear Engineering and Radiation Science, vol. 6, no. NERS-18-1132, 011402, pp. 1-12. https://doi.org/10.1115/1.4044000

APA

Sarotto, M., Firpo, G., Kochetkov, A., Krása, A., Fridman, E., & Cetnar, J. (2020). Neutronic analyses of the FREYA experiments in support of the ALFRED lead-cooled fast reactor core design and licensing. Journal of Nuclear Engineering and Radiation Science, 6(NERS-18-1132), 1-12. [011402]. https://doi.org/10.1115/1.4044000

Vancouver

Sarotto M, Firpo G, Kochetkov A, Krása A, Fridman E, Cetnar J. Neutronic analyses of the FREYA experiments in support of the ALFRED lead-cooled fast reactor core design and licensing. Journal of Nuclear Engineering and Radiation Science. 2020 Jan 5;6(NERS-18-1132):1-12. 011402. https://doi.org/10.1115/1.4044000

Author

Sarotto, Massimo ; Firpo, Gabriele ; Kochetkov, Anatoly ; Krása, Antonin ; Fridman, Emil ; Cetnar, Jerzy. / Neutronic analyses of the FREYA experiments in support of the ALFRED lead-cooled fast reactor core design and licensing. In: Journal of Nuclear Engineering and Radiation Science. 2020 ; Vol. 6, No. NERS-18-1132. pp. 1-12.

Bibtex - Download

@article{001011de39d84731a9203877a4009e10,
title = "Neutronic analyses of the FREYA experiments in support of the ALFRED lead-cooled fast reactor core design and licensing",
abstract = "During the EURATOM FP7 project FREYA, a number of experiments were performed in a critical core assembled in the VENUS-F zero-power reactor able to reproduce the ALFRED lead-cooled fast reactor spectrum in a dedicated island. The experiments dealt with the measurements of integral and local neutronic parameters, such as the core criticality, the control rod and the lead void reactivity worth, the axial distributions of fission rates for the nuclides of major interest in a fast spectrum, the spectral indices of important actinides (238U, 239Pu, 237Np) with respect to 235U. With the main aim to validate the neutronic codes adopted for the ALFRED core design, the VENUS-F core and its characterization measurements were simulated with both deterministic (ERANOS) and stochastic (MCNP, SERPENT) codes, by adopting different nuclear data libraries (JEFF, ENDF/B, JENDL, TENDL). This paper summarizes the main results obtained by highlighting a general agreement between measurements and simulations, with few discrepancies for some parameters that are discussed here. Additionally, a sensitivity and uncertainty analysis was performed with deterministic methods for the core reactivity: it clearly indicates that the small over-criticality estimated by the different codes/libraries resulted to be lower than the uncertainties due to nuclear data.",
keywords = "Fast neutron reactors, Nuclear fission, Nuclides, Uncertainty, Licensing, Neutrons, Rods, Spectra, Spectroscopy",
author = "Massimo Sarotto and Gabriele Firpo and Anatoly Kochetkov and Antonin Kr{\'a}sa and Emil Fridman and Jerzy Cetnar",
note = "Score=10",
year = "2020",
month = jan,
day = "5",
doi = "10.1115/1.4044000",
language = "English",
volume = "6",
pages = "1--12",
journal = "Journal of Nuclear Engineering and Radiation Science",
issn = "2332-8975",
publisher = "ASME - The American Society of Mechanical Engineers",
number = "NERS-18-1132",

}

RIS - Download

TY - JOUR

T1 - Neutronic analyses of the FREYA experiments in support of the ALFRED lead-cooled fast reactor core design and licensing

AU - Sarotto, Massimo

AU - Firpo, Gabriele

AU - Kochetkov, Anatoly

AU - Krása, Antonin

AU - Fridman, Emil

AU - Cetnar, Jerzy

N1 - Score=10

PY - 2020/1/5

Y1 - 2020/1/5

N2 - During the EURATOM FP7 project FREYA, a number of experiments were performed in a critical core assembled in the VENUS-F zero-power reactor able to reproduce the ALFRED lead-cooled fast reactor spectrum in a dedicated island. The experiments dealt with the measurements of integral and local neutronic parameters, such as the core criticality, the control rod and the lead void reactivity worth, the axial distributions of fission rates for the nuclides of major interest in a fast spectrum, the spectral indices of important actinides (238U, 239Pu, 237Np) with respect to 235U. With the main aim to validate the neutronic codes adopted for the ALFRED core design, the VENUS-F core and its characterization measurements were simulated with both deterministic (ERANOS) and stochastic (MCNP, SERPENT) codes, by adopting different nuclear data libraries (JEFF, ENDF/B, JENDL, TENDL). This paper summarizes the main results obtained by highlighting a general agreement between measurements and simulations, with few discrepancies for some parameters that are discussed here. Additionally, a sensitivity and uncertainty analysis was performed with deterministic methods for the core reactivity: it clearly indicates that the small over-criticality estimated by the different codes/libraries resulted to be lower than the uncertainties due to nuclear data.

AB - During the EURATOM FP7 project FREYA, a number of experiments were performed in a critical core assembled in the VENUS-F zero-power reactor able to reproduce the ALFRED lead-cooled fast reactor spectrum in a dedicated island. The experiments dealt with the measurements of integral and local neutronic parameters, such as the core criticality, the control rod and the lead void reactivity worth, the axial distributions of fission rates for the nuclides of major interest in a fast spectrum, the spectral indices of important actinides (238U, 239Pu, 237Np) with respect to 235U. With the main aim to validate the neutronic codes adopted for the ALFRED core design, the VENUS-F core and its characterization measurements were simulated with both deterministic (ERANOS) and stochastic (MCNP, SERPENT) codes, by adopting different nuclear data libraries (JEFF, ENDF/B, JENDL, TENDL). This paper summarizes the main results obtained by highlighting a general agreement between measurements and simulations, with few discrepancies for some parameters that are discussed here. Additionally, a sensitivity and uncertainty analysis was performed with deterministic methods for the core reactivity: it clearly indicates that the small over-criticality estimated by the different codes/libraries resulted to be lower than the uncertainties due to nuclear data.

KW - Fast neutron reactors

KW - Nuclear fission

KW - Nuclides

KW - Uncertainty

KW - Licensing

KW - Neutrons

KW - Rods

KW - Spectra

KW - Spectroscopy

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/38313705

U2 - 10.1115/1.4044000

DO - 10.1115/1.4044000

M3 - Article

VL - 6

SP - 1

EP - 12

JO - Journal of Nuclear Engineering and Radiation Science

JF - Journal of Nuclear Engineering and Radiation Science

SN - 2332-8975

IS - NERS-18-1132

M1 - 011402

ER -

ID: 6790214