Search scope:
排序： Display mode:
Liquid metal thermal hydraulics R&D at European scale: achievements and prospects
Frontiers in Energy 2021, Volume 15, Issue 4, Pages 842-853 doi: 10.1007/s11708-021-0743-2
Keywords： liquid metal thermal hydraulics Europe
Core designing of a new type of TVS-2M FAs: neutronics and thermal-hydraulics design basis limits
Saeed GHAEMI, Farshad FAGHIHI
Frontiers in Energy 2021, Volume 15, Issue 1, Pages 256-278 doi: 10.1007/s11708-018-0583-x
Keywords： FAs core design basis limits VVER-1000 analysis mixture of uranium-gadolinium oxides fuels thermal-hydraulics
Jinya KATSUYAMA, Shumpei UNO, Tadashi WATANABE, Yinsheng LI
Frontiers of Mechanical Engineering 2018, Volume 13, Issue 4, Pages 563-570 doi: 10.1007/s11465-018-0487-9
The thermal hydraulic (TH) behavior of coo-lant water is a key factor in the structural integrity assessments on reactor pressure vessels (RPVs) of pressurized water reactors (PWRs) under pressurized thermal shock (PTS) events, because the TH behavior may affect the loading conditions in the assessment. From the viewpoint of TH behavior, configuration of plant equipment and their dimensions, and operator action time considerably influence various parameters, such as the temperature and flow rate of coolant water and inner pressure. In this study, to investigate the influence of the operator action time on TH behavior during a PTS event, we developed an analysis model for a typical Japanese PWR plant, including the RPV and the main components of both primary and secondary systems, and performed TH analyses by using a system analysis code called RELAP5. We applied two different operator action times based on the Japanese and the United States (US) rules: Operators may act after 10 min (Japanese rules) and 30 min (the US rules) after the occurrence of PTS events. Based on the results of TH analysis with different operator action times, we also performed structural analyses for evaluating thermal-stress distributions in the RPV during PTS events as loading conditions in the structural integrity assessment. From the analysis results, it was clarified that differences in operator action times significantly affect TH behavior and loading conditions, as the Japanese rule may lead to lower stresses than that under the US rule because an earlier operator action caused lower pressure in the RPV.
Keywords： structural integrity reactor pressure vessel pressurized thermal shock thermal hydraulic analysis pressurized water reactor weld residual stress
Min PAN, Andrew PLUMMER
Frontiers of Mechanical Engineering 2018, Volume 13, Issue 2, Pages 225-231 doi: 10.1007/s11465-018-0509-7
This paper reviews recent developments in digital switched hydraulics particularly the switched inertance
Keywords： digital hydraulics switched inertance hydraulic systems energy efficiency high-speed switching valve
Key Technical Issues of TGP Permanent Shiplock
Fan Qixiang
Strategic Study of CAE 2004, Volume 6, Issue 1, Pages 48-52
Keywords： navigation structures water-conveyance system high and steep slope hydraulics
In-Vessel Melt Retention of Pressurized Water Reactors: Historical Review and Future Research Needs Review
Weimin Ma, Yidan Yuan, Bal Raj Sehgal
Engineering 2016, Volume 2, Issue 1, Pages 103-111 doi: 10.1016/J.ENG.2016.01.019
A historical review of in-vessel melt retention (IVR) is given, which is a severe accident mitigation measure extensively applied in Generation III pressurized water reactors (PWRs). The idea of IVR actually originated from the back-fitting of the Generation II reactor Loviisa VVER-440 in order to cope with the core-melt risk. It was then employed in the new deigns such as Westinghouse AP1000, the Korean APR1400 as well as Chinese advanced PWR designs HPR1000 and CAP1400. The most influential phenomena on the IVR strategy are in-vessel core melt evolution, the heat fluxes imposed on the vessel by the molten core, and the external cooling of the reactor pressure vessel (RPV). For in-vessel melt evolution, past focus has only been placed on the melt pool convection in the lower plenum of the RPV; however, through our review and analysis, we believe that other in-vessel phenomena, including core degradation and relocation, debris formation, and coolability and melt pool formation, may all contribute to the final state of the melt pool and its thermal loads on the lower head. By looking into previous research on relevant topics, we aim to identify the missing pieces in the picture. Based on the state of the art, we conclude by proposing future research needs.
Keywords： accident In-vessel melt retention Debris formation Debris remelting Melt pool formation Melt pool thermal-hydraulics
Title Author Date Type Operation
Core designing of a new type of TVS-2M FAs: neutronics and thermal-hydraulics design basis limits
Saeed GHAEMI, Farshad FAGHIHI
Journal Article
Influence evaluation of loading conditions during pressurized thermal shock transients based on thermal-hydraulics
Jinya KATSUYAMA, Shumpei UNO, Tadashi WATANABE, Yinsheng LI
Journal Article
京公网安备 11010502051620号
