Results 11 to 20 of about 8,242 (166)

Development of fracture toughness curve for PTS evaluation of reactor pressure vessels incorporating Master curve concept

open access: yesNihon Kikai Gakkai ronbunshu, 2019
The reactor pressure vessel is made of ferritic low alloy steel, which has fracture behaviors that include ductile to brittle transition temperature and decrease of fracture toughness in the beltline region of the reactor pressure vessel steel due to ...
Takatoshi HIROTA, Kentaro YOSHIMOTO
doaj   +1 more source

Analysis of the flow distribution and mixing characteristics in the reactor pressure vessel

open access: yesNuclear Engineering and Technology, 2021
The analysis of the fluid flow characteristics in reactor pressure vessel is an important part of the hydraulic design of nuclear power plant, which is related to the structure design of reactor internals, the flow distribution at core inlet and the ...
L.L. Tong, L.Q. Hou, X.W. Cao
doaj   +1 more source

Remote Monitoring of Equipment in Small Modular Reactors

open access: yesChemical Engineering Transactions, 2013
Small Modular Reactors (SMR) are being developed by several vendors for remote deployment and for small grid applications. These reactors have the additional advantage of load-following, process heat application, and improved safeguards features.
B. Upadhyaya   +3 more
doaj   +1 more source

Constraint-corrected fracture mechanics analysis of nozzle crotch corners in pressurized water reactors

open access: yesNuclear Engineering and Technology, 2022
This paper presents fracture mechanics analysis results for various cracks located at pressurized water reactor pressure vessel nozzle crotch corners taking into consideration constraint effect. Technical documents such as the ASME B&PV Code, Sec.XI were
Jong-Sung Kim   +5 more
doaj   +1 more source

WWER-1000 core loading characteristic influence on irradiation conditions of surveillance specimens and reactor pressure vessel [PDF]

open access: yesЯдерна фізика та енергетика, 2009
Irradiation conditions of WWER-1000 surveillance specimens and reactor pressure vessel are comparative analyzed for various core loadings. It is proved that the fluences onto specimens don't correlate with ones onto pressure vessel.
V. N. Bukanov   +4 more
doaj  

Numerical simulation on heat transfer in RPV lower head corium pools

open access: yesHe jishu, 2022
BackgroundIn-vessel Retention (IVR) refers to the prevention of pressure vessel melt-through failure by injecting cooling water into the gap between the pressure vessel and the heat insulation layer during a serious accident in a nuclear power plant ...
ZHU Guangyu   +4 more
doaj   +1 more source

Process of Air Ingress during a Depressurization Accident of GTHTR300

open access: yesScience and Technology of Nuclear Installations, 2018
A depressurization accident is the design-basis accidents of a gas turbine high temperature reactor, GTHTR300, which is JAEA’s design and one of the Very-High-Temperature Reactors (VHTR).
Tomoya Shiga   +2 more
doaj   +1 more source

Modernized surveillance program of the VVER-1000 reactor pressure vessel metal of the Ukrainian NPP unit [PDF]

open access: yesЯдерна фізика та енергетика
The surveillance program is an important source of information on the change in the properties of the metal of the water-water power reactor pressure vessel during operation.
O. V. Grytsenko   +8 more
doaj   +1 more source

Study on Hydraulic Characteristics of Reactor Coolant Pump Shutdown Transition Process Based on Primary Circuit Closed System

open access: yesFrontiers in Energy Research, 2022
According to the structural characteristics of a steam generator and a reactor pressure vessel, the reactor primary circuit system of HPR1000 is simplified to make the reactor coolant pump (RCP) characteristics match the resistance characteristics of the
Dong-hao Li   +5 more
doaj   +1 more source

Analysis of fission product source term release and decay heat under pressurized water reactor rupture accident

open access: yesHe jishu
BackgroundDuring severe reactor accidents, melten core causes the radioactive source term material to be no longer retained in the fuel but is released into the environment, causing serious radioactive contamination in the surrounding areas.PurposeThis ...
YUAN Xianbao   +6 more
doaj   +1 more source

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