Loading...
Search for:
accident-analysis
0.011 seconds
Domino effect in process-industry accidents - An inventory of past events and identification of some patterns
, Article Journal of Loss Prevention in the Process Industries ; Volume 24, Issue 5 , 2011 , Pages 575-593 ; 09504230 (ISSN) ; Abbasi, T ; Rashtchian, D ; Abbasi, S. A ; Sharif University of Technology
Abstract
The paper presents an inventory, perhaps the most comprehensive till date, of the major process-industry accidents involving 'domino effect'. The inventory includes, among other relevant information, the sequence of accidents that had occurred in each domino episode. The information has been analyzed to identify several patterns which may be useful in further work on understanding domino effect and reducing the probability of its occurrence in future. A concept of 'local domino effect' has been introduced
Development of a software for calculation of kinetic parameters of PWR reactors
, Article International Conference on Nuclear Engineering, Proceedings, ICONE, 17 May 2010 through 21 May 2010, Xi'an ; Volume 2 , 2010 ; 9780791849309 (ISBN) ; Boroushaki, M ; Nuclear Engineering Division ; Sharif University of Technology
2010
Abstract
In this research, new software package for neutronic calculations, especially kinetic parameters of PWR reactors, has been developed. The program used to link the WIMS-D5, BORGES and CITVAP nuclear codes has been written in Visual C# programming language. This software was used for calculation of kinetic parameters of WER-1000 and NOK Beznau reaction The ration (βeff)i/(βeff)corewhich are an important input data for the reactivity accident analysis, were also calculated. The results were compared with final safety analysis report (FSAR) and published documents. Copyright
Analysis of accumulators configuration in LB-LOCA for Bushehr NPP
, Article Annals of Nuclear Energy ; Volume 92 , 2016 , Pages 96-106 ; 03064549 (ISSN) ; Jafari, J ; Aghaie, M ; Vosoughi, N ; Nemati, M ; Sharif University of Technology
Elsevier Ltd
Abstract
This research focuses on a sensitivity analysis of accumulators configuration in a Large Break Loss of Coolant Accident (LB-LOCA) in Bushehr Nuclear Power Plant (BNPP). In this way, primary and secondary side components are modeled using RELAP5/MOD3.3 code. Having modeled the BNPP in a steady state hot full power operation, the thermal hydraulic consequences of a LB-LOCA in the reactor inlet is considered and sensitivity analysis for four major different configurations of accumulators are studied in detail. It is shown that any arrangement of accumulators in the Reactor Pressure Chamber (RPC) or Reactor Collection Chambers (RCC) leads to variation of fuel and clad temperatures during the...
Thesis Subject: Examining the Impacts of Objective and Subjective Variables on Occurrence And Severity of Accidents: A Case Study in Tehran
, M.Sc. Thesis Sharif University of Technology ; Kermanshah, Mohammad (Supervisor)
Abstract
Today, accidents are considered as one of the main causes of human mortality in the world. According to the World Health Organization, about 1.35 million people die in accidents each year, and 20 to 50 million people are injured because of accidents. In our country, about 17000 people are killed in traffic accidents annually. The mentioned statistics clarify the significance of paying attention to traffic accidents and identifying the factors that lead to them, as well as considering the strategies and policies for reducing accident rates. Due to the fundamental role of human factors in the occurrence of car accidents, the use of models that include the personality and attitude of drivers...
A comparative appraisal of roadway accident for Asia-Pacific countries
, Article International Journal of Engineering, Transactions A: Basics ; Volume 23, Issue 2 , 2010 , Pages 111-126 ; 17281431 (ISSN) ; Sharif University of Technology
Materials and Energy Research Center
2010
Abstract
This paper describes an attempt to shed some light on road safety in Asia Pacific region by characterizing and assessing its road accidents. The relevant national road accident data were extracted from centralized data sources of international agencies. Due to data incompleteness and missing values, 21 Asia Pacific countries, presenting more than half of the world's population, were selected for detailed analysis. The study database consisted of 7 variables, covering years 1980 and 1995. The univariate and multivariate statistical analyses for the selected countries showed interesting results and relations for the selected variables. Accident rates, reflecting road accident risk and...
Kinetic parameters evaluation of PWRs using static cell and core calculation codes
, Article Annals of Nuclear Energy ; Volume 41 , 2012 , Pages 110-114 ; 03064549 (ISSN) ; Malmir, H ; Sharif University of Technology
Abstract
In this paper, evaluation of the kinetic parameters (effective delayed neutron fraction and prompt neutron lifetime) in PWRs, using static cell and core calculation codes, is reported. A new software has been developed to link the WIMS, BORGES and CITATION codes in Visual C# computer programming language. Using the WIMS cell calculation code, multigroup microscopic cross-sections and number densities of different materials can be generated in a binary file. By the use of BORGES code, these binary-form cross-sections and number densities are converted to a format readable by the CITATION core calculation code, by which the kinetic parameters can be finally obtained. This software is used for...
Uncertainty evaluation of calculated and measured kinetics parameters of Tehran Research Reactor
, Article Nuclear Engineering and Design ; Volume 240, Issue 10 , 2010 , Pages 2761-2767 ; 00295493 (ISSN) ; Vosoughi, N ; Sharif University of Technology
Abstract
Effective delayed neutron fraction βeff and neutron generation time Λ are important factors in reactor physics calculation and transient analysis. In the first stage of this research, these kinetics parameters have been calculated for two states of Tehran Research Reactor (TRR), i.e. cold (fuel, clad and coolant temperature 20 °C) and hot (fuel, clad and coolant temperature 65, 49 and 44 °C, respectively) states using MTR-PC computer code. The ratio of (βeff) i/(βeff)core plays an important role in reactivity accident analysis codes. This parameter and its contribution to effective delayed neutron fraction from each nucleus have been calculated in cold and hot reactor states. Uncertainty of...
Flow Pattern Prediction in iPWR SMR with Natural Circulation by Coupling of RELAP and ANSYS CFX Code
, M.Sc. Thesis Sharif University of Technology ; Ghafari, Mohsen (Supervisor)
Abstract
Selection of appropriate thermohydraulic tool for analyzing nuclear reactors is a trade of between accuracy and calculation run-time. Nuclear reactors analyses perform on two levels including system and sub-channel. In this regard or the system codes' one-dimensional approach is selected or the CFD codes for considering the three-dimensional and non-equilibrium phenomenon are employed. In this research a T-H tool for prediction of light-water cooled reactors core is developed. Although this code requires lower CPU and run-time in comparison with CFD codes, in contrast with system codes can report non-equilibrium and three-dimensional phenomenon. This code has a modular implementation based...
Response planning for accidental oil spills in persian gulf: a decision support system (DSS) based on consequence modeling
, Article Marine Pollution Bulletin ; Volume 140 , 2019 , Pages 116-128 ; 0025326X (ISSN) ; Raie, M ; Sharif University of Technology
Elsevier Ltd
2019
Abstract
Different causes lead to accidental oil spills from fixed and mobile sources in the marine environment. Therefore, it is essential to have a systematic plan for mitigating oil spill consequences. In this research, a general DSS is proposed for passive and active response planning in Persian Gulf, before and after a spill. The DSS is based on NOAA's advanced oil spill model (GNOME), which is now linked with credible met-ocean datasets of CMEMS and ECMWF. The developed open-source tool converts the results of the Lagrangian oil spill model to quantitative parameters such as mean concentration and time of impact of oil. Using them, two new parameters, emergency response priority number (ERPN)...