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Relap5 Analysis of Processes in Reactor Cooling Circuit and Reactor Cavity in Case of Station Blackout in RBMK-1500
Reactor Cooling Circuit Reactor Cavity
2009/9/3
Ignalina NPP is equipped with channel-type boiling-water graphite-moderated reactor RBMK-1500. Results of the level-1 probabilistic safety assessment of the Ignalina NPP have shown that in topography ...
Regulatory Scenario for the Acceptance of Uncertainty Analysis Methodologies for the LB-LOCA and the Brazilian Approach
LB-LOCA Brazilian Approach
2009/9/3
The task of regulatory body staff reviewing and assessing a realistic large break loss-of-coolant accident evaluation model is discussed, facing the actual regulatory licensing environment related to ...
Deterministic Analysis of Natural Circulation Events at the Ignalina NPP
Natural Circulation NPP
2009/9/3
Eight main circulation pumps (MCPs) are employed for the cooling of water forced circulation through the RBMK-1500 reactor at the Ignalina nuclear power plant (NPP). These pumps are joined into groups...
Numerical Analysis of General Trends in Single-Phase Natural Circulation in a 2D-Annular Loop
General Trends Single-Phase Natural Circulation
2009/9/3
The aim of this paper is to address fluid flow behavior of natural circulation in a 2D-annular loop filled with water. A two-dimensional, numerical analysis of natural convection in a 2D-annular close...
SBWR Model for Steady-State and Transient Analysis
SBWR Model Steady-State Transient Analysis
2009/9/3
This paper presents a model of a simplified boiling water reactor (SBWR) to analyze the steady-state and transient behavior. The SBWR model is based on approximations of lumped and distributed paramet...
Comparison of Methods for Dependency Determination between Human Failure Events within Human Reliability Analysis
Human Failure Events Human Reliability Analysis
2009/9/3
The human reliability analysis (HRA) is a highly subjective evaluation of human performance, which is an input for probabilistic safety assessment, which deals with many parameters of high uncertainty...
The prediction of steam explosion inducing loads in nuclear power plants must be based on results of experimental research programmes and on simulations using validated fuel-coolant interaction codes....
Use of Nuclear Data Sensitivity and Uncertainty Analysis for the Design Preparation of the HCLL Breeder Blanket Mockup Experiment for ITER
Nuclear Data Design Preparation
2009/9/3
An experiment on a mockup of the test blanket module based on helium-cooled lithium lead (HCLL) concept will be performed in 2008 in the Frascati Neutron Generator (FNG) in order to study neutronics c...