Chilled Water System (CHWS-1) is an ITER safety cooling system comprised of two independent and segregated trains (CHWS-1A and CHWS-1B), which provide cooling water to components located in Tokamak and Hot Cell Complexes. VV-PHTS is the only component that, during water baking mode, operates at high pressure than CHWS-1. In case of leaks, it represents a risk in terms of over pressurization and contamination of the CHWS-1 (due to tritiated water and activated corrosion products (ACPs)). Therefore, this paper postulates CHWS-1 leak events at one interface: Vacuum Vessel Primary Heat Transfer System. (VV-PHTS). Three scenarios have been analysed: an incident event (heat exchanger pipe leakage) and two accident events (heat exchanger tube break and multiple tubes break). A simplified RELAP5–3D model of CHWS-1B was developed to perform thermal hydraulic transient analysis as well as to define and size system operation and control. A postulated accident management strategy is included while also defining CHWS-1 instrumentation and control (I&C), which play a relevant role in event detection and mitigation procedures. The simulation results are studied to analyze and verify the system behavior as well as the required actions to reach and maintain a safe state after the given events. With respect to the events studied, this paper reports and confirms the system design to properly and safely bring CHWS-1B to a shutdown, as per corresponding ITER project requirements. This operating scenario has been studied for academic purposes; it is not related to the actual CHWS-1B design. During VV-PHTS baking mode, decay HX is not foreseen to be operative. In order to avoid affecting the redundancy of the system, this study supports this decision.

Thermal hydraulic transient analysis of ITER chilled water system. Decay heat exchanger leak / Vicini, L.; Schiliuk, N.; Coscarelli, E.; Dell'Orco, G.; Caruso, G.. - In: FUSION ENGINEERING AND DESIGN. - ISSN 0920-3796. - 173:(2021), pp. 1-11. [10.1016/j.fusengdes.2021.112906]

Thermal hydraulic transient analysis of ITER chilled water system. Decay heat exchanger leak

Vicini L.
Primo
;
Caruso G.
2021

Abstract

Chilled Water System (CHWS-1) is an ITER safety cooling system comprised of two independent and segregated trains (CHWS-1A and CHWS-1B), which provide cooling water to components located in Tokamak and Hot Cell Complexes. VV-PHTS is the only component that, during water baking mode, operates at high pressure than CHWS-1. In case of leaks, it represents a risk in terms of over pressurization and contamination of the CHWS-1 (due to tritiated water and activated corrosion products (ACPs)). Therefore, this paper postulates CHWS-1 leak events at one interface: Vacuum Vessel Primary Heat Transfer System. (VV-PHTS). Three scenarios have been analysed: an incident event (heat exchanger pipe leakage) and two accident events (heat exchanger tube break and multiple tubes break). A simplified RELAP5–3D model of CHWS-1B was developed to perform thermal hydraulic transient analysis as well as to define and size system operation and control. A postulated accident management strategy is included while also defining CHWS-1 instrumentation and control (I&C), which play a relevant role in event detection and mitigation procedures. The simulation results are studied to analyze and verify the system behavior as well as the required actions to reach and maintain a safe state after the given events. With respect to the events studied, this paper reports and confirms the system design to properly and safely bring CHWS-1B to a shutdown, as per corresponding ITER project requirements. This operating scenario has been studied for academic purposes; it is not related to the actual CHWS-1B design. During VV-PHTS baking mode, decay HX is not foreseen to be operative. In order to avoid affecting the redundancy of the system, this study supports this decision.
2021
safety important; RELAP5–3D; thermal-hydraulic transient analysis; instrumentation & control; accident management strategy; ITER
01 Pubblicazione su rivista::01a Articolo in rivista
Thermal hydraulic transient analysis of ITER chilled water system. Decay heat exchanger leak / Vicini, L.; Schiliuk, N.; Coscarelli, E.; Dell'Orco, G.; Caruso, G.. - In: FUSION ENGINEERING AND DESIGN. - ISSN 0920-3796. - 173:(2021), pp. 1-11. [10.1016/j.fusengdes.2021.112906]
File allegati a questo prodotto
File Dimensione Formato  
Vicini_Thermal Hydraulic Transient Analysis_2021.pdf

solo gestori archivio

Tipologia: Versione editoriale (versione pubblicata con il layout dell'editore)
Licenza: Tutti i diritti riservati (All rights reserved)
Dimensione 5.15 MB
Formato Adobe PDF
5.15 MB Adobe PDF   Contatta l'autore
Vicini_Thermal Hydraulic Transient Analysis_postprint_2021.pdf

Open Access dal 02/01/2024

Tipologia: Documento in Post-print (versione successiva alla peer review e accettata per la pubblicazione)
Licenza: Creative commons
Dimensione 2.69 MB
Formato Adobe PDF
2.69 MB Adobe PDF

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11573/1605482
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus 0
  • ???jsp.display-item.citation.isi??? 0
social impact