Results 31 to 40 of about 272 (179)
Sensitivity Analysis of Continuous-energy Nuclear Data and Its Application in AP1000
Yuanzineng kexue jishu, 2022 AP1000 is the typical third-generation nuclear power technology. The sensitivity analysis of continuous-energy nuclear data for AP1000 is the basis of uncertainty quantification which plays an important role in subsequent safety analysis for AP1000 ...
HUANG Jinlong;CAO Liangzhi;HE Qingming;LI Jie;SHEN Wei
doaj
Casting process design and practice for coolant pump impeller in AP1000 nuclear power station [PDF]
China Foundry, 2020 The coolant pump impeller casting is the only rotating component in the nuclear island of an AP1000 nuclear power station, and is required to have a 60-year service time, which requires advanced materials and processing technologies to guarantee. In this
Ping Zhao, Zhong-li Liu, Gui-quan Wang
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Impact Analysis of Vanadium SPND Prompt Gamma Current in PWR-core Measurement
Yuanzineng kexue jishu, 2023 Vanadium self-powered neutron detector (SPND) is applied in Gen-Ⅲ commercial PWR AP1000 to simultaneously and continuously measure the in-core neutron flux density, and to control the safe and stable operation of nuclear reactors.
SHAO Ruizhi;CAO Liangzhi;LI Yunzhao;SI Fengwei;DU Chao
doaj
Performance Analysis of AP1000 Passive Systems during Direct Vessel Injection (DVI) Line Break
Atom Indonesia, 2016 Generation II Nuclear Power Plants (NPPs) have a design weakness as shown by the Fukushima accident. Therefore, Generation III+ NPPs are developed with focus on improvements of fuel technology and thermal efficiency, standardized design, and the use of ...
A.S. Ekariansyah, S. Widodo
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Wall-thickness reduction of AP1000 primary coolant pipes subjected to cold roll-forming
工程科学学报, 2016 A modified Johnson-Cook model was proposed based on the true stress-strain data of 316LN stainless steel and it was successfully used to describe the deformation characteristic of the steel at room temperature and low strain rate.
WANG Peng +3 more
doaj +1 more source
Nuclear Engineering and Technology, 2019 Seismic safety is considered to be one of the key design objectives of AP1000 nuclear power plant (NPP) in strong earthquakes. Dynamic behavior, damage development and aggravation effect are studied in this study for the three main components of AP1000 ...
Wanruo Chen +3 more
doaj +1 more source
Radiation shielding analysis and criticality safety calculation for spent fuel transportation cask [PDF]
EPJ Web of ConferencesChina anticipates a shortage in storage capacity for spent fuels at reactor sites for the AP1000 NPPs within the next 10 to 20 years. We proposed a conceptual design for a transportation cask capable of loading 21 spent fuel assemblies in AP1000 reactors
Chen Xiaosong +3 more
doaj +1 more source
The detection and diagnosis model for small scale MSLB accident
Nuclear Engineering and Technology, 2021 The main steam line break accident is an essential initiating event of the pressurized water reactor. In present work, the fuzzy set theory and the signal-based fault detection method has been used to detect the occurrence and diagnosis of the location ...
Meng Wang, Wenzhen Chen
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Numerical study on CMT boron replenishment strategy for an AP1000 nuclear power unit
Nuclear Engineering and Technology, 2022 The passive safety system is adopted in an AP1000 nuclear power unit to improve the operation safety of the whole unit. However, due to boron diffusion and periodic sampling, boron dilution occurs in the core makeup tank.
Hong Wang +3 more
doaj +1 more source
Development and Verification of a Spatial Dynamics Code RESTA‐3D for Light Water Reactors
International Journal of Energy Research, Volume 2025, Issue 1, 2025.A neutronics/thermal‐hydraulics (TH) coupled spatial dynamics code, reactor system transient analysis‐three dimensional (RESTA‐3D), has been developed for both static and transient analysis of large advanced light water reactors (LWRs), with a focus on control rod (CR) ejection accidents.
Yong Cui +4 more
wiley +1 more source