Preliminary steady and transient analysis for the CFETR helium cooled solid blanket system with RELAP
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S. Wang
Abstract
The helium cooled solid breeder (HCSB) blanket, which is one of the blanket candidates for Chinese Fusion Engineering Test Reactor (CFETR), has been developed in University of Science and Technology of China (USTC). And the blanket cooling system (HCS) is also designed for HCSB. The steady-state results show that the blanket system has a good relevance to the design parameters. The transient analysis of possible accidents should proceed to evaluate its safety performance. The accident analysis in this paper adopts the ITER-like conditions and the ex-vessel loss of coolant accident (LOCA) case is investigated with RELAP5 code. The results show that the ex-vessel LOCA with detection couldn't cause serious consequence, however the ex-vessel LOCA without detection has potential to melt the blanket that we should take measures to avoid it.
Kurzfassung
Das heliumgekühlte Feststoffbrutblanket (HCSB), das einer der Kandidaten für den sog. Chinese Fusion Engineering Test Reactor (CFETR) ist, wurde an der University of Science and Technology of China (USTC) entwickelt. Gleichzeitig wurde auch das Kühlsystem des Blankets (HCS) an diesen HCSB-Typ angepasst konzipiert. Stationäre Analysen zum Betriebsverhalten zeigen, dass dieses Blanketsystem nah an den Designparametern betrieben werden kann. Transiente Analysen möglicher Störfallszenarien werden zur Bewertung der Sicherheit durchgeführt. In diesem Beitrag werden RELAP5-Rechnungen für ein Störfallszenario dargestellt, bei dem ITER-ähnliche Anfangs- und Randbedingungen für das Ereignis Ex-Vessel Kühlmittelverluststörfall (ex-vessel LOCA) untersucht wurden. Die Ergebnisse zeigen, dass das Ex-Vessel LOCA-Ereignis, wenn es detektiert wird, keine schwerwiegenden Folgen haben wird. Die Rechnungen zeigen aber auch, dass ein Nichterkennen des Ereignisses zum Schmelzen von Blanketteilen führen kann, so dass es unumgänglich ist, geeignete Maßnahmen zur Vermeidung zu berücksichtigen.
References
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© 2018, Carl Hanser Verlag, München
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- Technical Contributions/Fachbeiträge
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- Proposal of a novel CHF correlation for PWR under low pressure conditions based on stepwise regression method
- Mechanistic prediction of post dryout heat transfer and rewetting
- Investigation of condensation process at COSMEA test facility with ATHLET code
- Research on thermal-hydraulic behavior in the spent fuel pool using a full-height experimental facility
- Experimental investigation on the distribution of spray water in a spent fuel-assembly simulator
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- Analysis code development for the direct reactor auxiliary cooling system of the pool-type sodium-cooled fast reactor
- Comparison of heat transfer models with databank of supercritical fluid
- Blankets – key element of a fusion reactor – functions, design and present state of development
- Preliminary steady and transient analysis for the CFETR helium cooled solid blanket system with RELAP
- A methodology for thermo-mechanical assessment of in-box LOCA events on fusion blankets and its application to EU DEMO HCPB breeding blanket
Articles in the same Issue
- Contents/Inhalt
- Contents
- Editorial
- 2nd Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology
- Technical Contributions/Fachbeiträge
- Challenging issues and recent R&D activities for enhancing nuclear safety in Korea
- Necessary improvements of the GRS simulation chain for the simulation of light-water-cooled SMRs
- Scaling analysis of core pressure drop in reduced height integral test facility
- Criteria and comparison of thermal stratification between PRHR HX heating and ADS spraying process in IRWST based on a down-scaled experimental facility
- Numerical simulation of bubble growth on and departure from the heated surface by an improved lattice Boltzmann model
- Improvements of interfacial friction and heat transfer models for rectangular narrow channel reflood simulation based on RELAP5
- Proposal of a novel CHF correlation for PWR under low pressure conditions based on stepwise regression method
- Mechanistic prediction of post dryout heat transfer and rewetting
- Investigation of condensation process at COSMEA test facility with ATHLET code
- Research on thermal-hydraulic behavior in the spent fuel pool using a full-height experimental facility
- Experimental investigation on the distribution of spray water in a spent fuel-assembly simulator
- Wet resuspension modelling and validation
- Analysis code development for the direct reactor auxiliary cooling system of the pool-type sodium-cooled fast reactor
- Comparison of heat transfer models with databank of supercritical fluid
- Blankets – key element of a fusion reactor – functions, design and present state of development
- Preliminary steady and transient analysis for the CFETR helium cooled solid blanket system with RELAP
- A methodology for thermo-mechanical assessment of in-box LOCA events on fusion blankets and its application to EU DEMO HCPB breeding blanket
