Abstract
Within the framework of EUROfusion research activities, the Karlsruhe Institute of Technology (KIT) is developing the Helium Cooled Pebble Bed (HCPB) breeding blanket (BB) for European demonstration fusion power plant (DEMO), with the support of BME and Wigner-RCP (Hungary) and CIEMAT (Spain). During the development of the BB concept in the past years, the in-box Loss Of Coolant Accident (LOCA) has been identified as a main design driver for BB. During this event, a leakage of pressurized coolant within the blanket box happens (in-box LOCA), pressurizing the blanket module and endangering its structural integrity. This accident has not been investigated in a detailed approach yet. In this paper, a more precise methodology is introduced taking into account the temperature evolution of the structure for assessing the structural integrity of BB under in-box LOCA and has been applied to the HCPB BB. The methodology and results are presented and critically discussed.
Kurzfassung
Im Rahmen der EUROfusion-Forschung entwickelt das Karlsruher Institut für Technologie (KIT) mit Unterstützung von BME und Wigner-RCP (Ungarn) und CIEMAT (Spanien) Helium Cooled Pebble Bed (HCPB) Brutblankets (BB) für das europäische Demonstrationsfusionskraftwerk (DEMO). Bei der Entwicklung des BB-Konzeptes in den vergangenen Jahren wurde der Kühlmittelverluststörfall (LOCA) innerhalb des Blankets als wichtigster Faktor der Designgebung des Blankets identifiziert. Während dieses Ereignisses tritt eine Leckage von unter Druck stehendem Kühlmittel innerhalb der Blanketbox auf (In-Box LOCA), wodurch das Blanket unter Druck gesetzt und seine strukturelle Integrität gefährdet wird. Dieser Unfall wurde noch nicht im Detail untersucht. In diesem Papier wird eine genauere Methodik beschrieben, die die Temperaturentwicklung der Struktur zur Beurteilung der strukturellen Integrität von BB unter In-Box-LOCA berücksichtigt und auf HCPB BB angewendet wurde. Die Methodik und Ergebnisse werden vorgestellt und kritisch diskutiert.
References
1 Federici, F.; et al.: European DEMO design strategy and consequences for materials. Nucl. Fusion57 (2017) 09200210.1088/1741-4326/57/9/092002Search in Google Scholar
2 Giancarli, L. M.; et al.: Progress and challenges of the ITER TBM Program from the IO perspective, Fusion Eng. Des.109–111 (2016)1491–1497Search in Google Scholar
3 Hernandez, F. et al.: Thermo-mechanical analyses and assessment with respect to the design codes and standards of the HCPB-TBM Breeder unit, Fusion Eng. Des.89 (2012) 1111–111710.1016/j.fusengdes.2012.02.088Search in Google Scholar
4 Pereslavtsev, P.; et al.: Neutronic analysis of the HCPB TBM in ITER utilizing an advanced integral approach, Fusion Eng. Des.85 (2010) 1653–165810.1016/j.fusengdes.2010.05.008Search in Google Scholar
5 Pereslavtsev, P.; et al.: Neutronic analyses for the optimization of the advanced HCPB breeder blanket design for DEMO, Fusion Eng. Des.124 (2017) 910–91410.1016/j.fusengdes.2017.01.028Search in Google Scholar
6 Zhou, G.; et al.: Preliminary steady state and transient thermal analysis of the new HCPB blanket for EU DEMO reactor, Int. J. Hydrogen Energ.41 (2016) 7047–705210.1016/j.ijhydene.2016.01.149Search in Google Scholar
7 Zhou, G.; et al.: Preliminary structural analysis of the new HCPB blanket for EU DEMO reactor, Int. J. Hydrogen Energ.41 (2016) 7053–705810.1016/j.ijhydene.2016.01.064Search in Google Scholar
8 Zhou, G.; et al.: Design study on the new EU DEMO HCPB breeding blanket: Thermal analysis, Prog. Nucl. Energy98 (2017) 167–17610.1016/j.pnucene.2017.03.013Search in Google Scholar
9 Zhou, G.; et al.: Transient thermal analysis and structural assessment of an ex-vessel LOCA event on the EU DEMO HCPB breeding blanket and the attachment system, Fusion Eng. Des. (2017) 10.1016/j.fusengdes.2017.12.017Search in Google Scholar
10 Zeile, C.; et al.: Structural assessment of the HCPB breeding blanket segments in the EU DEMO reactor under normal operation and a central plasma disruption, Fusion Eng. Des. (2018) 10.1016/j.fusengdes.2018.02.024Search in Google Scholar
11 Hernandez, F.; et al.: A new HCPB breeding blanket for the EU DEMO: Evolution, rationale and preliminary performances, Fusion Eng. Des.124 (2017) 882–88610.1016/j.fusengdes.2017.02.008Search in Google Scholar
12 Hernandez, F. A.; et al.: Overview of the HCPB Research Activities in EUROfusion, IEEE Trans. Plasma Sci. (2018) 10.1109/TPS.2018.2830813Search in Google Scholar
13 Cismondi, F.; et al.: HCPB TBM thermo mechanical design: Assessment with respect codes and standards and DEMO relevancy, Fusion Eng. Des.86 (2011) 2228–223210.1016/j.fusengdes.2011.02.067Search in Google Scholar
14 Aiello, G.; et al.: HCLL TBM design status and development, Fusion Eng. Des.86 (2011) 2129–213410.1016/j.fusengdes.2011.04.017Search in Google Scholar
15 Aubert, J.; et al.: Status on DEMO Helium Cooled Lithium Lead breeding blanket thermo-mechanical analyses, Fusion Eng. Des.109–111 (2016) 991–99510.1016/j.fusengdes.2016.01.037Search in Google Scholar
16 ASME: ASME's Boiler and Pressure Vessel Code (BPVC), ASME, USA, 2017Search in Google Scholar
17 AFCEN: RCC-MRx 2012: Design and construction rules for mechanical components of nuclear installations. Addenda included (2013), AFCEN, France, 201Search in Google Scholar
18 ITER: SDC-IC: Structural Design Criteria for In-vessel Components, ITER, France, 2012Search in Google Scholar
19 Aiello, G.: Impact of in-box LOCA on the blanket segment design, BB Design Review Meeting, Garching, Germany, 23 June, 2015Search in Google Scholar
© 2018, Carl Hanser Verlag, München
