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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...
GRS Method for Uncertainty and Sensitivity Evaluation of Code Results and Applications
GRS Code Results Applications
2009/9/3
During the recent years, an increasing interest in computational reactor safety analysis is to replace the conservative evaluation model calculations by best estimate calculations supplemented by unce...
Scaling, Uncertainty, and 3D Coupled Code Calculations in Nuclear Technology
Scaling Uncertainty 3D Coupled Code Calculations Nuclear Technology
2009/9/3
system codes such as RELAP, TRACE, CATHARE, or ATHLET are currently used by designer/vendors of NPPs, by utilities, licensing authorities, research organizations including universities, nuclear fuel c...
RELAP5/MOD3.3 Code Validation with Plant Abnormal Event
RELAP5/MOD3.3 Code Validation Plant Abnormal Event
2009/9/3
Measured plant data from various abnormal events are of great importance for code validation. The purpose of the study was to validate the RELAP5/MOD3.3 Patch 03 computer code with the abnormal event ...
Simulation of Boiling Flow Experiments Close to CHF with the Neptune_CFD Code
the Neptune_CFD Code Flow Experiments
2009/9/3
A three-dimensional two-fluid code Neptune_CFD has been validated against the Arizona State University (ASU) and DEBORA boiling flow experiments. Two-phase flow processes in the subcooled flow boiling...
Simulation of MASPn Experiments in MISTRA Test Facility with COCOSYS Code
COCOSYS Code MASPn Experiments
2009/9/3
An issue of the stratified atmospheres in the containments of nuclear power plants is still unresolved; different experiments are performed in the test facilities like TOSQAN and MISTRA. MASPn experim...
CFD Code Validation against Stratified Air-Water Flow Experimental Data
CFD Code Validation Air-Water Flow Experimental Data
2009/9/3
Pressurized thermal shock (PTS) modelling has been identified as one of the most important industrial needs related to nuclear reactor safety. A severe PTS scenario limiting the reactor pressure vesse...
Euler-Euler Large Eddy Simulation of a Square Cross-Sectional Bubble Column Using the Neptune_CFD Code
Euler-Euler Large Eddy the Neptune_CFD Code
2009/9/3
In this work, we report on Euler-Euler large eddy simulation (EELES) of dispersed bubbly flow in a square cross-sectional bubble column. Simulations are performed using the Neptune_CFD package, and re...
Modeling of Multisize Bubbly Flow and Application to the Simulation of Boiling Flows with the Neptune_CFD Code
Multisize Bubbly Flow Boiling Flows
2009/9/3
This paper describes the modeling of boiling multisize bubbly flows and its application to the simulation of the DEBORA experiment. We follow the method proposed originally by Kamp, assuming a given m...
Two-Phase Flow Simulations for PTS Investigation by Means of Neptune_CFD Code
Two-Phase Flow Simulations PTS
2009/9/3
Two-dimensional axisymmetric simulations of pressurized thermal shock (PTS) phenomena through Neptune_CFD module are presented aiming at two-phase models validation against experimental data. Because ...