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  • Experimental results of conductive inserts to reduce nuclear fuel . . .
    Post-irradiation examination of the experiment material was performed and included quantification of the extent of fracture in the fuel pellets It was found that the advanced-design pellets reduce the extent of fracture in a statistically significant way
  • Conductive inserts to reduce nuclear fuel temperature
    A series of experiments employing DRIFT and TREAT were performed to provide data on the extent and nature of fracture in fresh fuel at various points during a ramp to full power
  • Cracking in first ramp to power of standard versus high thermal . . .
    Post-irradiation examination of the experiment material was performed and included quantification of the extent of fracture in the fuel pellets It was found that the advanced-design pellets reduce the extent of fracture in a statistically significant way
  • Optimization of Conductive Fins to Minimize UO2 Fuel Temperature and . . .
    To further the development of low-enriched uranium fuels, precedence has been placed on delivering the same amount of power while lowering the fuel temperature and radial temperature gradient To address this, modeling efforts have resulted in a novel design featuring conductive fins of varying thermal conductivities and geometries inserted into the fuel matrix These conductive inserts were
  • DOE ID-Number - inldigitallibrary. inl. gov
    TREAT Experiments: Dry In-Pile Fracture Test (DRIFT) Concept: − Transient Reactor Test (TREAT) reactor used to provide volumetric heating through nuclear fission − Fuel stack is surrounded by a stainless steel heat sink known as the Dry In-Pile Fracture Test (DRIFT) fixture − Heat sink used as an inexpensive way to remove heat instead of
  • Optimization of Conductive Fins to Minimize UO2 Fuel Temperature and . . .
    Results The radial and temperature Discussion profile of the UO2 fuel pin is reported along the path bisecting any two By adjacent utilizing conductive the 2 56 million inserts, BISON as shown
  • Dry In-Pile Fracture Test (DRIFT) Data - Mendeley Data
    A series of experiments were performed in 2021 in Idaho National Laboratory’s (INL’s) Transient Test Facility (TREAT) to characterize fracture in light water reactor (LWR) fuel pellets These experiments, known as the Dry In-Pile Fracture Test (DRIFT) included both standard LWR fuel and a fuel concept consisting of thin fuel wafers separated by molybdenum disks for enhanced heat transfer
  • Experimental results of conductive inserts to reduce nuclear fuel . . .
    Article "Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating" Detailed information of the J-GLOBAL is an information service managed by the Japan Science and Technology Agency (hereinafter referred to as "JST") It provides free access to secondary information on researchers, articles, patents, etc , in science and technology
  • Anatomy of a Novel Irradiation Test: Structure and Process of the DRIFT . . .
    The DRIFT series of experiments at Idaho National Laboratory’s TREAT transient testing facility explored pellet cracking behavior in ceramic UO2 fuel pellets at LWR-relevant conditions to create data to support modeling and simulation of fuel performance
  • Mechanistic Verification of Empirical UO2 Fuel Fracture Models
    Fragmentation of the UO2 fuel pellets in nuclear rods starts with fracture early in their life, and increases with longer irradi-ation exposures Under normal operating conditions, fuel frac-ture is initially caused by the large thermal gradient induced in the fuel due to the low thermal conductivity of UO2
  • Experimental results of conductive inserts to reduce nuclear fuel . . .
    Dive into the research topics of 'Experimental results of conductive inserts to reduce nuclear fuel temperature during nuclear volumetric heating' Together they form a unique fingerprint





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