نتایج جستجو برای: loss of coolant accident
تعداد نتایج: 21191573 فیلتر نتایج به سال:
The performance of Cr-coated Optimized ZIRLO™ as accident tolerant fuel cladding material for pressurized water reactors (PWRs) is assessed. coating oxidation mechanisms, oxide stability, and the transformation Cr-coating/Optimized interface are among studied phenomena. For this purpose, samples were exposed at 1200°C in steam 3 min, 20 min 40 min. As-fabricated coated claddings, plus specimens...
Thin liquid wall fillTIs flowing under the influence of high-velocity turbulent gas streaIllS were studied for the purpose of obtaining an understanding of the Illechanics of filIll cooling. Conditions which insure liquid-filIll attachIllent to solid surfaces without loss of unevaporated liquid to the gas streaIll when siIllple radial-hole injectors are used were found; the IllaxiIlluIll allowa...
this thesis is a study on insurance fraud in iran automobile insurance industry and explores the usage of expert linkage between un-supervised clustering and analytical hierarchy process(ahp), and renders the findings from applying these algorithms for automobile insurance claim fraud detection. the expert linkage determination objective function plan provides us with a way to determine whi...
LIBRA-SP is a 1000 MWe light ion beam power reactor design study. The reactor structure is made of a low activation ferritic steel and uses LiPb as a breeder. The total activities in the blanket and reflector at shutdown are 721 MCi and 924 MCi, respectively. Hands-on maintenance is impossible anywhere inside the reactor chamber. The biological dose rates near the diode are too high at all time...
Activation and safety analyses were performed for the ARIES-ST design. The ARIES-ST power plant includes a water cooled copper center post and uses a SiC/LiPb blanket. The first wall and shield are made of low activation ferritic steel and cooled with helium. The center post, first wall, inboard shield and blanket were assumed to survive for 2.6 full power years (FPY). On the other hand, the ou...
Abstract The safety injection system (RIS)is a large and complex fluid in nuclear power plant. Its central role is to ensure the of core event breach first circuit In order investigate timing safe at time Small-Break Loss-Of-Coolant Accident (SBLOCA), this paper uses GO-FLOW method model seven points three operational phases system. calculation completed conjunction with failure rate each compo...
Today, most software applications, also in the nuclear field, come with a graphical user interface. Recently, the Symbolic Nuclear Analysis Package (SNAP) was designed to simplify the process of performing safety analysis. The purpose of the present study was to develop an SNAP animation model for RELAP5 calculations of a nuclear installation. The facility selected was the Rig of Safety Assessm...
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