Bulk fluid std film resistance sfr là gì
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This page is a formulary only. See formularies with cost estimates. Drug searchMore formulary informationChecking your browser before accessing pnk5u11de22.xn--80aukdeb.xn--p1ai.This process is automatic. Your browser will redirect to your requested content shortly. Please allow up to 3 seconds... Bad Bot protection by AntiBot.Cloud Your IP: 64.233.173.44 Shin, Sang Hun; Kim, Jun Hwan; Kim, June-Hyung; Ryu, Woo Seog; Park, Sang Gyu; Kim, Sung Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of) 2015-10-15 Nowadays, in Korea, advanced cladding such as FC92 is developed and its transient behaviors are required for the safety analysis of SFR. Design and safety analyses of sodium-cooled fast reactor (SFR) require understanding fuel pin responses to a wide range of off-normal events. In a loss-of-flow (LOF) or transient over-power (TOP), the temperature of the cladding is rapidly increased above its steady-state service temperature. Transient tests have been performed in sections of fuel pin cladding and a large data base has been established for austenitic stainless steel such as 20% cold-worked 316 SS and ferritic/martensitic steels such as HT9. This paper summarizes the technical status of transient testing facilities and their results. Previous researches showed the transient behaviors of HT9 cladding. For the safety analyses in SFR in Korea, simulated transient tests with newly developed FC92 as well as HT9 cladding are being carried out.
Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions Energy Technology Data Exchange (ETDEWEB) Park, Dong Jun, E-mail: [email protected]; Kim, Hyun Gil; Jung, Yang Il; Park, Jung Hwan; Yang, Jae Ho; Koo, Yang Hyun |