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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...
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...
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 ...
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...
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。