Keywords: CBS, computer based system; NPP, nuclear power plant; PHWR, pressurized heavy water reactor; SDS, Shutdown system; FAV, fast acting valve; LPIS, liquid poison injection system; HMI, human machine interface; LC, logic condition; RTOS, real time operating s
مقالات ISI (ترجمه نشده)
مقالات زیر هنوز به فارسی ترجمه نشده اند.
در صورتی که به ترجمه آماده هر یک از مقالات زیر نیاز داشته باشید، می توانید سفارش دهید تا مترجمان با تجربه این مجموعه در اسرع وقت آن را برای شما ترجمه نمایند.
در صورتی که به ترجمه آماده هر یک از مقالات زیر نیاز داشته باشید، می توانید سفارش دهید تا مترجمان با تجربه این مجموعه در اسرع وقت آن را برای شما ترجمه نمایند.
Self-sufficient nuclear fuel technology development and applications
Keywords: PWR, Pressurized Water Reactor; PHWR, Pressurized Heavy Water Reactor; KNF, KEPCO Nuclear Fuel; KAERI, Korea Atomic Energy Research Institute; WEC, Westinghouse Electric Company; CHF, critical heat flux; FA, fuel assembly; LTA, Lead Test Assembly; LOCA, L
Studies on flow induced vibration of reactivity devices of 700 MWe Indian PHWR
Keywords: PHWR, pressurized heavy water reactor; CFD, computational fluid dynamics; FEM, Finite element method; PIU, poison injection unit; ZCU, liquid zone control unit; ξ, material damping
A study on the grid-to-rod fretting wear-induced fuel failure observed in the 16×16KOFA fuel
Keywords: KNF, Korea Nuclear Fuel; PWR, pressurized water reactor; PHWR, pressurized heavy water reactor; KOFA, Korean Optimized Fuel Assembly; GTRFW, grid-to-rod fretting wear; FIV, fluid-induced vibration; FR, fuel rod; FA, fuel assembly
Thermal consideration of CANDU-SCWR sliding pressure startup through subchannel analysis
Keywords: ATHAS, advanced thermal-hydraulics analysis subchannel; BWR, boiling water reactor; CANDU, CANada Deuterium Uranium; CHF, critical heat flux; FPP, fossilfired power plant; LWR, light water reactor; PDO, post-dry out; PHWR, pressurized heavy water reactor;
Development of an advanced PWR fuel for OPR1000s in Korea
Keywords: PWR, pressurized water reactor; PHWR, pressurized heavy water reactor; LWR, light water reactor; OPR1000, optimized power reactor 1000 MWe; KNF, Korea Nuclear Fuel; SG, spacer grid; FA, fuel assembly; FR, fuel rod; GT, guide thimble tube; LTA, lead test a
Evaluation of N,N,N′,N′-tetraoctyl-3-oxapentane-diamide (TODGA) as a mobile carrier in remediation of nuclear waste using supported liquid membrane
Keywords: D.F., decontamination factor; LWR, light water reactor; PHWR, pressurized heavy water reactor; PTFE, poly tetra fluoro ethylene; SHLW, simulated high level waste; SLM, supported liquid membrane; TODGA, N,N,N’,N’-tetraoctyl-3-oxapentane-diamideTODGA; Liqui