Test matrices definition for the SIRIO facility in the frame of the H2020-PIACE project: Pre-test simulation and conclusions

Tewfik Hamidouche; Rafaël Fernandez; Fabio Gianetti; Vencenzo Narcisi; Martina Molinari; Andrea Achilli; César Queral; Pierdomenico Lorusso; Daniele Mazzi; Luminita Nitulescu; Marco Caramello; Michele Frignani; Mariano Tarantino; Gonzalo Jimenez; Ivo Kljenak; Jure Oder

Test matrices definition for the SIRIO facility in the frame of the H2020-PIACE project: Pre-test simulation and conclusions

Tewfik Hamidouche, Rafaël Fernandez, Fabio Gianetti, Vencenzo Narcisi, Martina Molinari, Andrea Achilli, César Queral, Pierdomenico Lorusso, Daniele Mazzi, Luminita Nitulescu, Marco Caramello, Michele Frignani, Mariano Tarantino, Gonzalo Jimenez, Ivo Kljenak, Jure Oder

Reactor Safety

Research output › peer-review

Abstract

Passive safety is one of Generation IV nuclear plants leading pillars. In this perspective, several new passive safety systems have been proposed and tested to demonstrate their inherence passive safety features for the GEN IV reactor technologies under development. For Lead Fast Reactor (LFR), a self-regulating system, referred to as Isolation Condenser (IC) passive safety system, is considered to ensure long-term safe state without needs for external actions or energy supply. The IC concept is able to remove the decay heat, in order to both reach a safe shutdown state and reduce the power removal capabilities over time delaying primary cooling freezing. This IC devoted safety function is achieved by allowing the Decay Heat Removal system (DHR) loop to be flooded by Non-Condensable (NC) gases when needed (at low pressure) to passively control the rate of energy transfer via condensation in the heat exchange components. The concept is applicable to water-cooled reactors as well, to limit the temperature decrease rate during accidental events, hence reducing the thermal stresses on the primary and secondary system components. The HORIZON 2020 Passive IsolAtion CondEnser (PIACE) project, started in 2019, aims at testing the IC passive safety system in a new experimental facility, at SIET premises in Piacenza (Italy). An experimental program is defined to test the applicability of the IC concept for selected reactor technologies: LFR, MYRRHA ADS, PWR, BWR, PHWR. Pre-test simulations were run to provide a comprehensive evidence of the applicability of the IC solution for these technologies, and confirmed its efficiency. Test matrices have been defined for the SIRIO experimental campaign. The paper presents the pre-test simulations performed with system thermal-hydraulic codes to demonstrate that the proposed DHR solution is able to accomplish the DHR safety function for the particular case of liquid metal fast reactors technologies: ALFRED and MYRRHA ADS.

Original language	English
Title of host publication	Technical meeting on State-of-the-art Thermal Hydraulics of Fast Reactors
Publisher	IAEA - International Atomic Energy Agency
Number of pages	11
State	Published - 30 Sep 2022
Event	2022 - IAEA Technical meeting on state-of-the-art thermal hydraulics of fast reactors - C.R. ENEA, Camugnano Duration: 26 Sep 2022 → 30 Sep 2022 https://conferences.iaea.org/event/239/

Conference

Conference	2022 - IAEA Technical meeting on state-of-the-art thermal hydraulics of fast reactors
Country/Territory	Italy
City	Camugnano
Period	2022-09-26 → 2022-09-30
Internet address	https://conferences.iaea.org/event/239/

Access to Document

https://conferences.iaea.org/event/239/contributions/23977/License: Unspecified

Cite this

Hamidouche, T., Fernandez, R., Gianetti, F., Narcisi, V., Molinari, M., Achilli, A., Queral, C., Lorusso, P., Mazzi, D., Nitulescu, L., Caramello, M., Frignani, M., Tarantino, M., Jimenez, G., Kljenak, I., & Oder, J. (2022). Test matrices definition for the SIRIO facility in the frame of the H2020-PIACE project: Pre-test simulation and conclusions. In Technical meeting on State-of-the-art Thermal Hydraulics of Fast Reactors IAEA - International Atomic Energy Agency. https://conferences.iaea.org/event/239/contributions/23977/

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title = "Test matrices definition for the SIRIO facility in the frame of the H2020-PIACE project: Pre-test simulation and conclusions",

abstract = "Passive safety is one of Generation IV nuclear plants leading pillars. In this perspective, several new passive safety systems have been proposed and tested to demonstrate their inherence passive safety features for the GEN IV reactor technologies under development. For Lead Fast Reactor (LFR), a self-regulating system, referred to as Isolation Condenser (IC) passive safety system, is considered to ensure long-term safe state without needs for external actions or energy supply. The IC concept is able to remove the decay heat, in order to both reach a safe shutdown state and reduce the power removal capabilities over time delaying primary cooling freezing. This IC devoted safety function is achieved by allowing the Decay Heat Removal system (DHR) loop to be flooded by Non-Condensable (NC) gases when needed (at low pressure) to passively control the rate of energy transfer via condensation in the heat exchange components. The concept is applicable to water-cooled reactors as well, to limit the temperature decrease rate during accidental events, hence reducing the thermal stresses on the primary and secondary system components. The HORIZON 2020 Passive IsolAtion CondEnser (PIACE) project, started in 2019, aims at testing the IC passive safety system in a new experimental facility, at SIET premises in Piacenza (Italy). An experimental program is defined to test the applicability of the IC concept for selected reactor technologies: LFR, MYRRHA ADS, PWR, BWR, PHWR. Pre-test simulations were run to provide a comprehensive evidence of the applicability of the IC solution for these technologies, and confirmed its efficiency. Test matrices have been defined for the SIRIO experimental campaign. The paper presents the pre-test simulations performed with system thermal-hydraulic codes to demonstrate that the proposed DHR solution is able to accomplish the DHR safety function for the particular case of liquid metal fast reactors technologies: ALFRED and MYRRHA ADS.",

keywords = "Passive decay heat removal, LFR, MYRRHA ADS, PIACE, Isolation condenser",

author = "Tewfik Hamidouche and Rafa{\"e}l Fernandez and Fabio Gianetti and Vencenzo Narcisi and Martina Molinari and Andrea Achilli and C{\'e}sar Queral and Pierdomenico Lorusso and Daniele Mazzi and Luminita Nitulescu and Marco Caramello and Michele Frignani and Mariano Tarantino and Gonzalo Jimenez and Ivo Kljenak and Jure Oder",

note = "Score=3; 2022 - IAEA Technical meeting on state-of-the-art thermal hydraulics of fast reactors ; Conference date: 26-09-2022 Through 30-09-2022",

year = "2022",

month = sep,

day = "30",

language = "English",

booktitle = "Technical meeting on State-of-the-art Thermal Hydraulics of Fast Reactors",

publisher = "IAEA - International Atomic Energy Agency",

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Hamidouche, T , Fernandez, R, Gianetti, F, Narcisi, V, Molinari, M, Achilli, A, Queral, C, Lorusso, P, Mazzi, D, Nitulescu, L, Caramello, M, Frignani, M, Tarantino, M, Jimenez, G, Kljenak, I & Oder, J 2022, Test matrices definition for the SIRIO facility in the frame of the H2020-PIACE project: Pre-test simulation and conclusions. in Technical meeting on State-of-the-art Thermal Hydraulics of Fast Reactors. IAEA - International Atomic Energy Agency, 2022 - IAEA Technical meeting on state-of-the-art thermal hydraulics of fast reactors, Camugnano, Italy, 2022-09-26. <https://conferences.iaea.org/event/239/contributions/23977/>

TY - GEN

T1 - Test matrices definition for the SIRIO facility in the frame of the H2020-PIACE project

T2 - 2022 - IAEA Technical meeting on state-of-the-art thermal hydraulics of fast reactors

AU - Hamidouche, Tewfik

AU - Fernandez, Rafaël

AU - Gianetti, Fabio

AU - Narcisi, Vencenzo

AU - Molinari, Martina

AU - Achilli, Andrea

AU - Queral, César

AU - Lorusso, Pierdomenico

AU - Mazzi, Daniele

AU - Nitulescu, Luminita

AU - Caramello, Marco

AU - Frignani, Michele

AU - Tarantino, Mariano

AU - Jimenez, Gonzalo

AU - Kljenak, Ivo

AU - Oder, Jure

N1 - Score=3

PY - 2022/9/30

Y1 - 2022/9/30

N2 - Passive safety is one of Generation IV nuclear plants leading pillars. In this perspective, several new passive safety systems have been proposed and tested to demonstrate their inherence passive safety features for the GEN IV reactor technologies under development. For Lead Fast Reactor (LFR), a self-regulating system, referred to as Isolation Condenser (IC) passive safety system, is considered to ensure long-term safe state without needs for external actions or energy supply. The IC concept is able to remove the decay heat, in order to both reach a safe shutdown state and reduce the power removal capabilities over time delaying primary cooling freezing. This IC devoted safety function is achieved by allowing the Decay Heat Removal system (DHR) loop to be flooded by Non-Condensable (NC) gases when needed (at low pressure) to passively control the rate of energy transfer via condensation in the heat exchange components. The concept is applicable to water-cooled reactors as well, to limit the temperature decrease rate during accidental events, hence reducing the thermal stresses on the primary and secondary system components. The HORIZON 2020 Passive IsolAtion CondEnser (PIACE) project, started in 2019, aims at testing the IC passive safety system in a new experimental facility, at SIET premises in Piacenza (Italy). An experimental program is defined to test the applicability of the IC concept for selected reactor technologies: LFR, MYRRHA ADS, PWR, BWR, PHWR. Pre-test simulations were run to provide a comprehensive evidence of the applicability of the IC solution for these technologies, and confirmed its efficiency. Test matrices have been defined for the SIRIO experimental campaign. The paper presents the pre-test simulations performed with system thermal-hydraulic codes to demonstrate that the proposed DHR solution is able to accomplish the DHR safety function for the particular case of liquid metal fast reactors technologies: ALFRED and MYRRHA ADS.

AB - Passive safety is one of Generation IV nuclear plants leading pillars. In this perspective, several new passive safety systems have been proposed and tested to demonstrate their inherence passive safety features for the GEN IV reactor technologies under development. For Lead Fast Reactor (LFR), a self-regulating system, referred to as Isolation Condenser (IC) passive safety system, is considered to ensure long-term safe state without needs for external actions or energy supply. The IC concept is able to remove the decay heat, in order to both reach a safe shutdown state and reduce the power removal capabilities over time delaying primary cooling freezing. This IC devoted safety function is achieved by allowing the Decay Heat Removal system (DHR) loop to be flooded by Non-Condensable (NC) gases when needed (at low pressure) to passively control the rate of energy transfer via condensation in the heat exchange components. The concept is applicable to water-cooled reactors as well, to limit the temperature decrease rate during accidental events, hence reducing the thermal stresses on the primary and secondary system components. The HORIZON 2020 Passive IsolAtion CondEnser (PIACE) project, started in 2019, aims at testing the IC passive safety system in a new experimental facility, at SIET premises in Piacenza (Italy). An experimental program is defined to test the applicability of the IC concept for selected reactor technologies: LFR, MYRRHA ADS, PWR, BWR, PHWR. Pre-test simulations were run to provide a comprehensive evidence of the applicability of the IC solution for these technologies, and confirmed its efficiency. Test matrices have been defined for the SIRIO experimental campaign. The paper presents the pre-test simulations performed with system thermal-hydraulic codes to demonstrate that the proposed DHR solution is able to accomplish the DHR safety function for the particular case of liquid metal fast reactors technologies: ALFRED and MYRRHA ADS.

KW - Passive decay heat removal

KW - LFR

KW - MYRRHA ADS

KW - PIACE

KW - Isolation condenser

UR - https://ecm.sckcen.be/OTCS/llisapi.dll/open/53065641

M3 - In-proceedings paper

BT - Technical meeting on State-of-the-art Thermal Hydraulics of Fast Reactors

PB - IAEA - International Atomic Energy Agency

Y2 - 26 September 2022 through 30 September 2022

ER -