Results 41 to 50 of about 2,771 (221)
The present work develops and analysis the main parameters of a test section for natural convection in case of failure of the pumping system as much as the loss of coolant in refrigeration accidents.
Luis Felipe Serra Cadiz +3 more
doaj +1 more source
According to the characteristics of the reactor internal structure of nuclear power plants, the vibration of the secondary core support pillar in water can be modeled as the vibration of the cantilever beam structure under the action of transverse flow, and its first beam mode is highly likely to be activated.
Xiaowen Wang, Yixian Zhou, Leon Cizelj
wiley +1 more source
Casting process design and practice for coolant pump impeller in AP1000 nuclear power station [PDF]
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
doaj +1 more source
Sensitivity Analysis of Continuous-energy Nuclear Data and Its Application in AP1000
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
Nuclear Power: a Hedge against Uncertain Gas and Carbon Prices? [PDF]
High fossil fuel prices have rekindled interest in nuclear power. This paper identifies specific nuclear characteristics making it unattractive to merchant generators in liberalised electricity markets, and argues that non-fossil fuel technologies have ...
David M. Newbery +4 more
core +3 more sources
Systematic study of autocorrelation time in pure SU(3) lattice gauge theory
Results of our autocorrelation measurement performed on Fujitsu AP1000 are reported. We analyze (i) typical autocorrelation time, (ii) optimal mixing ratio between overrelaxation and pseudo-heatbath and (iii) critical behavior of autocorrelation time ...
A. Nakamura +14 more
core +1 more source
Development and Verification of a Spatial Dynamics Code RESTA‐3D for Light Water Reactors
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
Huge water storage tank on the top of many buildings may affect the safety of the structure caused by fluid-structure interaction (FSI) under the earthquake.
Daogang Lu, Yu Liu, Xiaojia Zeng
doaj +1 more source
A review of the status of the Areva European Prssurised Water Reactor (EPR)
Thomas, Stephen
core
Small leaks within a nuclear power plant can escalate into significant leaks, leading to plant shutdown and substantial losses if operational limits are exceeded. Thus, the demand for systems that can rapidly detect minor leaks is increasing. Current research seeks to address this need.
Dae Kyung Choi +6 more
wiley +1 more source

