搜索结果: 1-15 共查到“核科学技术 Thermal”相关记录15条 . 查询时间(0.283 秒)
THERMAL TEXTURE SELECTION AND CORRECTION FOR BUILDING FACADE INSPECTION BASED ON THERMAL RADIANT CHARACTERISTICS
building facade thermal image calibration texture mapping terrestrial 3D model
2018/6/4
An automatic building façade thermal texture mapping approach, using uncooled thermal camera data, is proposed in this paper. First, a shutter-less radiometric thermal camera calibration method i...
Dynamics of Quark Gluon Plasma and Interference of Thermal Photons
Dynamics of Quark Gluon Plasma Interference of Thermal Photons Nuclear Theory
2011/10/11
Abstract: The quantum statistical interference between identical particles emitted from a completely chaotic source is expected to provide valuable input for the space time description of the system. ...
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...
Characterization and Application of the Thermal Neutron Radiography Beam in the Egyptian Second Experimental and Training Research Reactor (ETRR-2)
Egyptian Second Experimental Training Research Reactor
2009/9/3
The Experimental, Training, Research Reactor (ETRR-2) is an open-pool multipurpose reactor (MPR) with a core power of 22 MWth cooled and moderated by light water and reflected with beryllium. It...
Approaches, Relevant Topics, and Internal Method for Uncertainty Evaluation in Predictions of Thermal-Hydraulic System Codes
Uncertainty Evaluation Thermal-Hydraulic System Codes
2009/9/3
The evaluation of uncertainty constitutes the necessary supplement of best-estimate calculations performed to understand accident scenarios in water-cooled nuclear reactors. The needs come from the im...
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...
Analyses of Instability Events in the Peach Bottom-2 BWR Using Thermal-Hydraulic and 3D Neutron Kinetic Coupled Codes Technique
3D Neutron Kinetic Codes Technique
2009/9/3
Boiling water reactor (BWR) instabilities may occur when, starting from a stable operating condition, changes in system parameters bring the reactor towards an unstable region. In order to design more...
Thermal-Hydraulic System Codes in Nulcear Reactor Safety and Qualification Procedures
Thermal-Hydraulic System Codes Nulcear Reactor
2009/9/3
In the last four decades, large efforts have been undertaken to provide reliable thermal-hydraulic system codes for the analyses of transients and accidents in nuclear power plants. Whereas the first ...
Bootstrap and Order Statistics for Quantifying Thermal-Hydraulic Code Uncertainties in the Estimation of Safety Margins
Thermal-Hydraulic Code Safety Margins
2009/9/3
In the present work, the uncertainties affecting the safety margins estimated from thermal-hydraulic code calculations are captured quantitatively by resorting to the order statistics and the bootstra...
International Course to Support Nuclear Licensing by User Training in the Areas of Scaling, Uncertainty, and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes: 3D S.UN.COP Seminars
Nuclear Licensing 3D Thermal-Hydraulics/Neutron-Kinetics
2009/9/3
Thermal-hydraulic system computer codes are extensively used worldwide for analysis of nuclear facilities by utilities, regulatory bodies, nuclear power plant designers, vendors, and research organiza...
An Overview of the Pressurized Thermal Shock Issue in the Context of the NURESIM Project
Pressurized Thermal Shock the NURESIM Project
2009/9/3
Within the European Integrated Project NURESIM, the simulation of PTS is investigated. Some accident scenarios for Pressurized Water Reactors may cause Emergency Core Coolant injection into the cold l...
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...
CFD Simulation of Thermal-Hydraulic Benchmark V1000CT-2 Using ANSYS CFX
CFD Thermal-Hydraulic
2009/9/3
Plant measured data from VVER-1000 coolant mixing experiments were used within the OECD/NEA and AER coupled code benchmarks for light water reactors to test and validate computational fluid dynamic (C...
GCFR Coupled Neutronic and Thermal-Fluid-Dynamics Analyses for a Core Containing Minor Actinides
GCFR Thermal-Fluid-Dynamics
2009/9/2
Problems about future energy availability, climate changes, and air quality seem to play an important role in energy production. While current reactor generations provide a guaranteed and economical e...
先进型沸水堆的热工水力设计和热工裕量(The Thermal Hydraulic Design and Thermal Margins of Advanced Boiling Water Reactor )
先进型沸水堆 热工水力设计 热工裕量
2008/10/8
简要介绍先进型沸水堆（ABWR）热工水力设计的特点、安全限值与热工裕量及热工水力设计与URD的符合性。