Results 51 to 60 of about 272 (179)
Sensitivity Evaluation of AP1000 Nuclear Power Plant Best Estimation Model
The best estimation process of AP1000 Nuclear Power Plant (NPP) requires proper selections of parameters and models so as to obtain the most accurate results compared with the actual design parameters.
Hao Shi, Qi Cai, Yuqing Chen
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It is essential to predict the radioactivity distribution around the reactor cooling system (RCS) during obligatory cyclic operation of AP-1000. A home-developed program CPA-AP1000 is upgraded to predict the response of activated corrosion products (ACPs)
Fiaz Mahmood +4 more
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The Critical Heat Flux (CHF) of water with dispersed alumina nanoparticles was measured for the geometry and flow conditions relevant to the In-Vessel Retention (IVR) situation which can occur during core melting sequences in certain advanced Light Water
G. DEWITT +4 more
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Reliability Study of the AP1000 Passive Safety System by Fuzzy Approach
The Westinghouse AP1000 is a new design nuclear power plant which has implemented the concept of passive system. Even though a passive system may be more reliable than an active one, the possibility of the passive system to fail still exists.
D.T. Sony Tjahyani
doaj
Numerical investigation of the thermal-hydraulic characteristics of AP1000 steam generator U-tubes
Steam generators (SGs) are vital heat exchangers that connect the primary and secondary sides in power plant systems. Based on the AP1000 SG, a numerical model of SG U-tubes is developed.
Zeng-Guang Sui +3 more
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Components of nuclear power plants do not always have historical failure data to probabilistically evaluate their reliability characteristics. To overcome this drawback, an alternative approach has been proposed by involving experts to qualitatively ...
J.H. Purba
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The AP1000 Plant and the China Project Commissioning Success [PDF]
The AP1000® (Advanced Plant) is a 1100-MWel-class Pressurized Water Reactor (PWR) with innovative passive-safety features and extensive plant simplifications that enhance construction, operation, maintenance, and safety with reduced plant costs. The passive-safety features of the plant use natural driving forces such as pressurized gas, gravity flow ...
openaire +1 more source
Study of the Reactor Control System of MSHIM in AP1000
According to the mechanism analysis and simulation of power control system of MSHIM in AP1000, a modified MSHIM (Mechanical Shim) control strategy is presented, which employs the error between the reactor coolant average temperature and its reference ...
Xinyu Wei, Fuyu Zhao
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The General Design and Technology Innovations of CAP1400
The pressurized water reactor CAP1400 is one of the sixteen National Science and Technology Major Projects. Developed from China's nuclear R&D system and manufacturing capability, as well as AP1000 technology introduction and assimilation, CAP1400 is an ...
Mingguang Zheng +5 more
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Assessment of radiation exposure and public health before and after the operation of Sanmen nuclear power plant. [PDF]
Ren H +14 more
europepmc +1 more source

