IAEA'S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS

Ikoleta Morelová; Florent Heidet; Ivan Di Piazza; Xiaoyan Yang; Antoine Gerschenfeld; Natesan Kumaresan; Jae Ho Jeong; Andrei Volkov; Rodolfo Vaghetto; Vladimir Kriventsev; David W. Wootan; H. Hassan; Jin Wang; Soeren Kliem; Fabio Giannetti; Jonggan Hong; Janne Wallenius; Olu Omotowa; Tyler Sumner; Andrew M. Casella; Pierdomenico Lorusso; Daogang Lu; Emil Fridman; Alessandro Petruzzi; Marek Stempniewicz; Carlo Fiorina; Joseph Kelly; Anton Moisseytsev; J. V. Nelson; Daniele Martelli; Dalin Zhang; Andrei Rineiski; Masaaki Tanaka; Sergey Tsaun; Konstantin Mikityuk; Jeffrey Lane

IAEA'S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS

Ikoleta Morelová
, Florent Heidet
, Ivan Di Piazza
, Xiaoyan Yang
, Antoine Gerschenfeld
, Natesan Kumaresan
, Jae Ho Jeong
, Andrei Volkov
, Rodolfo Vaghetto
, Vladimir Kriventsev
, David W. Wootan
, H. Hassan
, Jin Wang
, Soeren Kliem
, Fabio Giannetti
, Jonggan Hong
, Janne Wallenius
, Olu Omotowa
, Tyler Sumner
, Andrew M. Casella

Pierdomenico Lorusso, Daogang Lu, Emil Fridman, Alessandro Petruzzi, Marek Stempniewicz, Carlo Fiorina, Joseph Kelly, Anton Moisseytsev, J. V. Nelson, Daniele Martelli, Dalin Zhang, Andrei Rineiski, Masaaki Tanaka, Sergey Tsaun, Konstantin Mikityuk, Jeffrey Lane

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

2 Scopus citations

Abstract

A Coordinated Research Project on “Benchmark Analysis of FFTF Loss of Flow Without Scram Test” was launched by the International Atomic Energy Agency (IAEA) in 2018. A series of passive safety tests were conducted from 1980-1992 at the Fast Flux Test Facility (FFTF), 400 MW(th) liquid sodium cooled nuclear test reactor owned by U.S. Department of Energy (DOE) to demonstrate the potential of FFTF to survive severe accident initiators with no core damage. Amongst these tests was a series of Loss of Flow Without Scram (LOFWOS) tests from power levels up to 50%, also commonly referred to as Unprotected Loss of Flow (ULOF) tests, which were studied in the IAEA CRP. The data were provided by the Argonne National Laboratory (ANL) and Pacific Northwest National Laboratory (PNNL). Another Research Coordinated Project on “Benchmark of Transition from Forced to Natural Circulation Experiment with Heavy Liquid Metal Loop” was launched by the IAEA in 2022. Three tests were conducted in 2017 to study the thermal-hydraulic behavior of a test fuel assembly cooled by lead-bismuth eutectic alloy during transition from forced to natural convection at the NACIE-UP facility at Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA), Italy. This project is the first IAEA CRP that is dedicated to the thermal hydraulics of lead and lead bismuth eutectic (LBE) technology. The paper provides a general overview of the two CRPs within the framework of the IAEA activities on thermal hydraulics of fast reactors.

Original language	English
Title of host publication	Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables
Subtitle of host publication	United to Provide Carbon Neutral Power", ICONE 2023
Publisher	American Society of Mechanical Engineers (ASME)
ISBN (Print)	9784888982566
State	Published - 1 Jan 2023
Externally published	Yes
Event	30th International Conference on Nuclear Engineering, ICONE 2023 - Kyoto, Japan Duration: 21 May 2023 → 26 May 2023

Publication series

Name	International Conference on Nuclear Engineering, Proceedings, ICONE
Volume	2023-May

Conference

Conference	30th International Conference on Nuclear Engineering, ICONE 2023
Country/Territory	Japan
City	Kyoto
Period	21/05/23 → 26/05/23

Keywords

Fast Reactors
IAEA
LFR
Modelling and Simulation Coordinated Research Project
SFR
Thermal Hydraulics

ASJC Scopus subject areas

Nuclear Energy and Engineering

Cite this

Morelová, I., Heidet, F., Di Piazza, I., Yang, X., Gerschenfeld, A., Kumaresan, N., Jeong, J. H., Volkov, A., Vaghetto, R., Kriventsev, V., Wootan, D. W., Hassan, H., Wang, J., Kliem, S., Giannetti, F., Hong, J., Wallenius, J., Omotowa, O., Sumner, T., ... Lane, J. (2023). IAEA'S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS. In Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023 (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 2023-May). American Society of Mechanical Engineers (ASME).

Morelová, Ikoleta ; Heidet, Florent ; Di Piazza, Ivan et al. / IAEA'S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS. Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023. American Society of Mechanical Engineers (ASME), 2023. (International Conference on Nuclear Engineering, Proceedings, ICONE).

@inproceedings{882dea11419a4d58a32a4859276df6c8,

title = "IAEA'S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS",

abstract = "A Coordinated Research Project on {\textquotedblleft}Benchmark Analysis of FFTF Loss of Flow Without Scram Test{\textquotedblright} was launched by the International Atomic Energy Agency (IAEA) in 2018. A series of passive safety tests were conducted from 1980-1992 at the Fast Flux Test Facility (FFTF), 400 MW(th) liquid sodium cooled nuclear test reactor owned by U.S. Department of Energy (DOE) to demonstrate the potential of FFTF to survive severe accident initiators with no core damage. Amongst these tests was a series of Loss of Flow Without Scram (LOFWOS) tests from power levels up to 50\%, also commonly referred to as Unprotected Loss of Flow (ULOF) tests, which were studied in the IAEA CRP. The data were provided by the Argonne National Laboratory (ANL) and Pacific Northwest National Laboratory (PNNL). Another Research Coordinated Project on {\textquotedblleft}Benchmark of Transition from Forced to Natural Circulation Experiment with Heavy Liquid Metal Loop{\textquotedblright} was launched by the IAEA in 2022. Three tests were conducted in 2017 to study the thermal-hydraulic behavior of a test fuel assembly cooled by lead-bismuth eutectic alloy during transition from forced to natural convection at the NACIE-UP facility at Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA), Italy. This project is the first IAEA CRP that is dedicated to the thermal hydraulics of lead and lead bismuth eutectic (LBE) technology. The paper provides a general overview of the two CRPs within the framework of the IAEA activities on thermal hydraulics of fast reactors.",

keywords = "Fast Reactors, IAEA, LFR, Modelling and Simulation Coordinated Research Project, SFR, Thermal Hydraulics",

author = "Ikoleta Morelov{\'a} and Florent Heidet and \{Di Piazza\}, Ivan and Xiaoyan Yang and Antoine Gerschenfeld and Natesan Kumaresan and Jeong, \{Jae Ho\} and Andrei Volkov and Rodolfo Vaghetto and Vladimir Kriventsev and Wootan, \{David W.\} and H. Hassan and Jin Wang and Soeren Kliem and Fabio Giannetti and Jonggan Hong and Janne Wallenius and Olu Omotowa and Tyler Sumner and Casella, \{Andrew M.\} and Pierdomenico Lorusso and Daogang Lu and Emil Fridman and Alessandro Petruzzi and Marek Stempniewicz and Carlo Fiorina and Joseph Kelly and Anton Moisseytsev and Nelson, \{J. V.\} and Daniele Martelli and Dalin Zhang and Andrei Rineiski and Masaaki Tanaka and Sergey Tsaun and Konstantin Mikityuk and Jeffrey Lane",

note = "Publisher Copyright: {\textcopyright} 2023 by JSME.; 30th International Conference on Nuclear Engineering, ICONE 2023 ; Conference date: 21-05-2023 Through 26-05-2023",

year = "2023",

month = jan,

day = "1",

language = "English",

isbn = "9784888982566",

series = "International Conference on Nuclear Engineering, Proceedings, ICONE",

publisher = "American Society of Mechanical Engineers (ASME)",

booktitle = "Proceedings of the 30th International Conference on Nuclear Engineering {"}Nuclear, Thermal, and Renewables",

}

Morelová, I, Heidet, F, Di Piazza, I, Yang, X, Gerschenfeld, A, Kumaresan, N, Jeong, JH, Volkov, A, Vaghetto, R, Kriventsev, V, Wootan, DW, Hassan, H, Wang, J, Kliem, S, Giannetti, F, Hong, J, Wallenius, J, Omotowa, O, Sumner, T, Casella, AM, Lorusso, P, Lu, D, Fridman, E, Petruzzi, A, Stempniewicz, M, Fiorina, C, Kelly, J, Moisseytsev, A, Nelson, JV, Martelli, D, Zhang, D, Rineiski, A, Tanaka, M, Tsaun, S, Mikityuk, K & Lane, J 2023, IAEA'S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS. in Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023. International Conference on Nuclear Engineering, Proceedings, ICONE, vol. 2023-May, American Society of Mechanical Engineers (ASME), 30th International Conference on Nuclear Engineering, ICONE 2023, Kyoto, Japan, 21/05/23.

IAEA'S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS. / Morelová, Ikoleta; Heidet, Florent; Di Piazza, Ivan et al.
Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023. American Society of Mechanical Engineers (ASME), 2023. (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 2023-May).

Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review

TY - GEN

T1 - IAEA'S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS

AU - Morelová, Ikoleta

AU - Heidet, Florent

AU - Di Piazza, Ivan

AU - Yang, Xiaoyan

AU - Gerschenfeld, Antoine

AU - Kumaresan, Natesan

AU - Jeong, Jae Ho

AU - Volkov, Andrei

AU - Vaghetto, Rodolfo

AU - Kriventsev, Vladimir

AU - Wootan, David W.

AU - Hassan, H.

AU - Wang, Jin

AU - Kliem, Soeren

AU - Giannetti, Fabio

AU - Hong, Jonggan

AU - Wallenius, Janne

AU - Omotowa, Olu

AU - Sumner, Tyler

AU - Casella, Andrew M.

AU - Lorusso, Pierdomenico

AU - Lu, Daogang

AU - Fridman, Emil

AU - Petruzzi, Alessandro

AU - Stempniewicz, Marek

AU - Fiorina, Carlo

AU - Kelly, Joseph

AU - Moisseytsev, Anton

AU - Nelson, J. V.

AU - Martelli, Daniele

AU - Zhang, Dalin

AU - Rineiski, Andrei

AU - Tanaka, Masaaki

AU - Tsaun, Sergey

AU - Mikityuk, Konstantin

AU - Lane, Jeffrey

PY - 2023/1/1

Y1 - 2023/1/1

N2 - A Coordinated Research Project on “Benchmark Analysis of FFTF Loss of Flow Without Scram Test” was launched by the International Atomic Energy Agency (IAEA) in 2018. A series of passive safety tests were conducted from 1980-1992 at the Fast Flux Test Facility (FFTF), 400 MW(th) liquid sodium cooled nuclear test reactor owned by U.S. Department of Energy (DOE) to demonstrate the potential of FFTF to survive severe accident initiators with no core damage. Amongst these tests was a series of Loss of Flow Without Scram (LOFWOS) tests from power levels up to 50%, also commonly referred to as Unprotected Loss of Flow (ULOF) tests, which were studied in the IAEA CRP. The data were provided by the Argonne National Laboratory (ANL) and Pacific Northwest National Laboratory (PNNL). Another Research Coordinated Project on “Benchmark of Transition from Forced to Natural Circulation Experiment with Heavy Liquid Metal Loop” was launched by the IAEA in 2022. Three tests were conducted in 2017 to study the thermal-hydraulic behavior of a test fuel assembly cooled by lead-bismuth eutectic alloy during transition from forced to natural convection at the NACIE-UP facility at Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA), Italy. This project is the first IAEA CRP that is dedicated to the thermal hydraulics of lead and lead bismuth eutectic (LBE) technology. The paper provides a general overview of the two CRPs within the framework of the IAEA activities on thermal hydraulics of fast reactors.

AB - A Coordinated Research Project on “Benchmark Analysis of FFTF Loss of Flow Without Scram Test” was launched by the International Atomic Energy Agency (IAEA) in 2018. A series of passive safety tests were conducted from 1980-1992 at the Fast Flux Test Facility (FFTF), 400 MW(th) liquid sodium cooled nuclear test reactor owned by U.S. Department of Energy (DOE) to demonstrate the potential of FFTF to survive severe accident initiators with no core damage. Amongst these tests was a series of Loss of Flow Without Scram (LOFWOS) tests from power levels up to 50%, also commonly referred to as Unprotected Loss of Flow (ULOF) tests, which were studied in the IAEA CRP. The data were provided by the Argonne National Laboratory (ANL) and Pacific Northwest National Laboratory (PNNL). Another Research Coordinated Project on “Benchmark of Transition from Forced to Natural Circulation Experiment with Heavy Liquid Metal Loop” was launched by the IAEA in 2022. Three tests were conducted in 2017 to study the thermal-hydraulic behavior of a test fuel assembly cooled by lead-bismuth eutectic alloy during transition from forced to natural convection at the NACIE-UP facility at Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA), Italy. This project is the first IAEA CRP that is dedicated to the thermal hydraulics of lead and lead bismuth eutectic (LBE) technology. The paper provides a general overview of the two CRPs within the framework of the IAEA activities on thermal hydraulics of fast reactors.

KW - Fast Reactors

KW - IAEA

KW - LFR

KW - Modelling and Simulation Coordinated Research Project

KW - SFR

KW - Thermal Hydraulics

UR - https://www.scopus.com/pages/publications/85178505274

M3 - Conference contribution

AN - SCOPUS:85178505274

SN - 9784888982566

T3 - International Conference on Nuclear Engineering, Proceedings, ICONE

BT - Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables

PB - American Society of Mechanical Engineers (ASME)

T2 - 30th International Conference on Nuclear Engineering, ICONE 2023

Y2 - 21 May 2023 through 26 May 2023

ER -

Morelová I, Heidet F, Di Piazza I, Yang X, Gerschenfeld A, Kumaresan N et al. IAEA'S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS. In Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023. American Society of Mechanical Engineers (ASME). 2023. (International Conference on Nuclear Engineering, Proceedings, ICONE).

IAEA'S COORDINATED RESEARCH PROJECTS ON THERMAL HYDRAULICS OF FAST REACTORS

Abstract

Publication series

Conference

Keywords

ASJC Scopus subject areas

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