The Westinghouse Lead Fast Reactor (LFR) is a 450 MWe class, lead-cooled, fast neutron spectrum, pool-type reactor with passive safety systems. Its mission is to best complement Light Water Reactors (LWR) in the mid- to long-term by providing enhanced application versatility for global markets while targeting cost-effective deployment. The passive heat removal system (PHRS) is the emergency decay heat removal system of this advanced plant. A distinctive feature of the PHRS that it is always on, and does not require any operator intervention, signals of intelligence or moving is parts for the actuation and operation, consistent with the IAEA passive safety category B. The system initially removes heat through water boiling and subsequently transitions to (indefinite) air cooling. To assess the performance of the PHRS and provide experimental data for the verification and validation of modeling and simulation tools, the passive heat removal facility (PHRF) has been built at the Ansaldo Nuclear’s site in Wolverhampton, UK, with the support from the United Kingdom Government and international partners. The PHRF is a full-height separate effects test facility that follows the power-to-volume scaling rule to maximize its prototypicality. The test matrix of the first phase of testing included both air cooling tests and transition tests from water cooling to air cooling. A significant amount of experimental data has been generated in the first phase of testing, confirming the performance of the PHRS both in air cooling mode and during the transition from water cooling to air cooling.

First phase passive heat removal facility (PHRF) experiments for westinghouse LFR / Liao, Jun; Caramello, Marco; Durse, Megan; Wright, Richard; Tatli, Emre; Ferroni, Paolo; Khalil Youssef, Giorgio; Frignani, Michele; Tarantino, Mariano; Wimshurst, Aiden; Watkins, Rhodri; Macpherson, Graham. - (2024), pp. 685-694. (Intervento presentato al convegno 2024 International Congress on Advances in Nuclear Power Plants, ICAPP 2024 tenutosi a Las Vegas; USA) [10.13182/t130-44221].

First phase passive heat removal facility (PHRF) experiments for westinghouse LFR

Khalil Youssef, Giorgio;
2024

Abstract

The Westinghouse Lead Fast Reactor (LFR) is a 450 MWe class, lead-cooled, fast neutron spectrum, pool-type reactor with passive safety systems. Its mission is to best complement Light Water Reactors (LWR) in the mid- to long-term by providing enhanced application versatility for global markets while targeting cost-effective deployment. The passive heat removal system (PHRS) is the emergency decay heat removal system of this advanced plant. A distinctive feature of the PHRS that it is always on, and does not require any operator intervention, signals of intelligence or moving is parts for the actuation and operation, consistent with the IAEA passive safety category B. The system initially removes heat through water boiling and subsequently transitions to (indefinite) air cooling. To assess the performance of the PHRS and provide experimental data for the verification and validation of modeling and simulation tools, the passive heat removal facility (PHRF) has been built at the Ansaldo Nuclear’s site in Wolverhampton, UK, with the support from the United Kingdom Government and international partners. The PHRF is a full-height separate effects test facility that follows the power-to-volume scaling rule to maximize its prototypicality. The test matrix of the first phase of testing included both air cooling tests and transition tests from water cooling to air cooling. A significant amount of experimental data has been generated in the first phase of testing, confirming the performance of the PHRS both in air cooling mode and during the transition from water cooling to air cooling.
2024
2024 International Congress on Advances in Nuclear Power Plants, ICAPP 2024
LFR; passive safety; testing; thermal hydraulics
04 Pubblicazione in atti di convegno::04b Atto di convegno in volume
First phase passive heat removal facility (PHRF) experiments for westinghouse LFR / Liao, Jun; Caramello, Marco; Durse, Megan; Wright, Richard; Tatli, Emre; Ferroni, Paolo; Khalil Youssef, Giorgio; Frignani, Michele; Tarantino, Mariano; Wimshurst, Aiden; Watkins, Rhodri; Macpherson, Graham. - (2024), pp. 685-694. (Intervento presentato al convegno 2024 International Congress on Advances in Nuclear Power Plants, ICAPP 2024 tenutosi a Las Vegas; USA) [10.13182/t130-44221].
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11573/1732381
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