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GELATIO: a general framework for modular digital analysis of high-purity Ge detector signals
GELATIO modular digital analysis high-purity Ge detector signals
2011/7/21
GELATIO is a new software framework for advanced data analysis and digital signal processing developed for the GERDA neutrinoless double beta decay experiment. The framework is tailored to handle the ...
Thermal-Hydraulic Analysis of Coolant Flow Decrease in Fuel Channels of Smolensk-3 RBMK during GDH Blockage Event
Thermal-Hydraulic Coolant Flow
2009/9/3
One of the transients that have received considerable attention in the safety evaluation of RBMK reactors is the partial break of a group distribution header (GDH). The coolant flow rate blockage in o...
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 ...
Thermal-Hydraulic Analysis Tasks for ANAV NPPs in Support of Plant Operation and Control
Thermal-Hydraulic ANAV NPPs
2009/9/3
Thermal-hydraulic analysis tasks aimed at supporting plant operation and control of nuclear power plants are an important issue for the Asociación Nuclear Ascó-Vandellòs (ANAV). ANAV is the consortium...
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...
Dynamic Analysis of Coolant Channel and Its Internals of Indian 540 MWe PHWR Reactor
Coolant Channel Indian 540 MWe PHWR Reactor
2009/9/3
The horizontal coolant channel is one of the important parts of primary heat transport system in PHWR type of reactors. There are in all 392 channels in the core of Indian 540 MWe reactor. Each ...
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....
Decay Heat Removal and Transient Analysis in Accidental Conditions in the EFIT Reactor
Decay Heat Removal the EFIT Reactor
2009/9/3
The development of a conceptual design of an industrial-scale transmutation facility (EFIT) of several 100 MW thermal power based on accelerator-driven system (ADS) is addressed in the frame of ...
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...
CFD Analysis of a Slug Mixing Experiment Conducted on a VVER-1000 Model
CFD VVER-1000 Model
2009/9/3
A commercial CFD code was applied, for validation purposes, to the simulation of a slug mixing experiment carried out at OKB “Gidropress” scaled facility in the framework of EC TACIS project R2.02/02:...
Thermal Hydraulic Analysis of a Passive Residual Heat Removal System for an Integral Pressurized Water Reactor
Reactor Thermal Hydraulic
2009/9/3
A theoretical investigation on the thermal hydraulic characteristics of a new type of passive residual heat removal system (PRHRS), which is connected to the reactor coolant system via the secondary s...