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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Ensembles of climate change models for risk assessment of nuclear power plants [PDF]
, 2017 Climate change affects technical Systems, Structures and Infrastructures (SSIs), changing the environmental context for which SSI were originally designed.
Al-Dahidi S +10 more
core +4 more sources
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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Non-Markovian Persistence at the PC point of a 1d non-equilibrium kinetic Ising model [PDF]
, 1997 One-dimensional non-equilibrium kinetic Ising models evolving under the competing effect of spin flips at zero temperature and nearest neighbour spin exchanges exhibiting a parity-conserving (PC) phase transition on the level of kinks are investigated ...
Blundell R E +12 more
core +1 more source
A Comparison in Thermal-hydraulics Analysis of Pwr1000 Using Fixed and Temperature Function of Thermal Conductivity [PDF]
, 2016 A COMPARISON IN THERMAL-HYDRAULICS ANALYSIS OF PWR-1000 USING FIXEDAND TEMPERATURE FUNCTION OF THERMAL CONDUCTIVITY. A study to analyze theinfluence of the fuel-cladding's thermal conductivity on the sub-channel of pressurized waterreactor 1000 (PWR-1000)
Isnaini, M. D. (Muhammad) +1 more
core +2 more sources
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