Injury Criteria Based Optimisation of Automobile Passive Safety Systems to Mitigate the Effects of Full-Frontal Automobile Collisions

2014 ◽  
Author(s):  
Volkan Esat
Keyword(s):  
Interior Design ◽  
Simulation Software ◽  
Safety System ◽  
Passive Safety ◽  
Steering Wheel ◽  
System Parameters ◽  
Passive Safety Systems ◽  
Injury Criteria ◽  
Passive Safety System ◽  
Safety Systems

Passive safety systems such as airbags, seat belts, and interior structural design of the automobile play a significant role in injury prevention of the occupant during collisions. Important design and operation parameters of the passive safety systems such as airbag firing times and steering wheel position as an interior design attribute potentially affect the dynamics of the occupant during impact and determine the amount of mitigation of a possible injury. This research aims to contribute towards improving passive safety systems in automobile design for mitigation of injuries by optimising the features and parameters of various subsystems such as driver’s airbag and steering wheel. Two separate computational models, a 5th percentile female and a 50th percentile male, comprising of a typical automobile interior with passive safety systems are constructed in the specialised impact simulation software MADYMO. Two different crash pulses of 30 kph and 48 kph are applied to the computational human body models in full-frontal crashes. Passive safety system parameters; in particular, airbag firing times and steering wheel column angles, are varied to investigate their effects on the head, neck and upper torso through injury criteria. Injury criteria predictions are employed in optimisation algorithms to figure out the best combinations for passive safety system parameters in order to mitigate possible injuries for all drivers.

scholarly journals PECULIARITIES OF CONDUCTING FORENSIC RESEARCH ON PASSENGER SRS VEHICLE SYSTEM TO ESTABLISH THE REASON NOT CAUSE THE FRONT BUCKLES

2019 ◽  
Vol 19 (1) ◽  
pp. 309-319
Author(s):  
V. Varlahov ◽  
A. Lubentsov
Keyword(s):  
Technical Condition ◽  
Safety System ◽  
Passive Safety ◽  
Vehicle Electrical System ◽  
Passive Safety Systems ◽  
Road Users ◽  
Passive Safety System ◽  
The One ◽  
Safety Systems ◽  
Serious Injuries

Issues that arise from experts during the performance of court automotive expert assessments (expert researches) of technical condition of automobiles are considered, namely: SRS passive safety systems. The sequence of carrying out elemental research of the passive safety system of the SRS of cars on establishing the reasons for failure of the front (front) airbag of the passenger during a traffic accident is presented. The urgency of this paper is due, on the one hand, to the mass installation of airbags on cars of different brands, which are intended to protect the driver and passengers of vehicles from injuries during a collision, and on the other hand, frequent cases of not triggering airbags in the collision, associated as both for technical and operational reasons, resulting in serious injuries to the driver and passengers in the event of a collision. The increase in the level of constructive safety of the car, above all, is ensured by strengthening the requirements for the development, installation of structural elements and systems that provide protection of life and health of road users. Given the diversity of sources of risk factors for road accidents, constructive safety is divided into active, passive and after emergency. The examination of the technical condition of the SRS passive safety system is essentially a study of the vehicle electrical system requiring safety measures, since damage to the insulation of wires, shorting of individual circuits of electrical wires, and the introduction of extraneous current to the connectors can lead to the deployment of airbags during research.

Investigation of effects of nonavailability of passive safety systems on the reactor behaviour during LOCA Scenario in AP600

Kerntechnik ◽  
2021 ◽  
Vol 86 (3) ◽  
pp. 244-255
Author(s):  
S. H. Abdel-Latif ◽  
A. M. Refaey
Keyword(s):  
Passive Safety ◽  
Primary System ◽  
Water Storage Tank ◽  
The Core ◽  
Passive Safety Systems ◽  
Loss Of Coolant Accident ◽  
Passive Safety System ◽  
Stage 4 ◽  
Core Cooling ◽  
Safety Systems

Abstract The AP600 is a Westinghouse Advanced Passive PWR with a two–loop 1 940 MWt. This reactor is equipped with advanced passive safety systems which are designed to operate automatically at desired set-points. On the other hand, the failure or nonavailability to operate of any of the passive safety systems may affect reactor safety. In this study, modeling and nodalization of primary and secondary loops, and all passive reactor cooling systems are conducted and a 10-inch cold leg break LOCA is analyzed using ATHLET 3.1A Code. During loss of coolant accident in which the passive safety system failure or nonavailability are considered, four different scenarios are assumed. Scenario 1 with the availability of all passive systems, scenario 2 is failure of one of the accumulators to activate, scenario 3 is without actuation of the automatic depressurization system (ADS) stages 1–3, and scenario 4 is without actuation of ADS stage 4. Results indicated that the actuation of passive safety systems provide sufficient core cooling and thus could mitigate the accidental consequence of LOCAs. Failure of one accumulator during LOCA causes early actuation of ADS and In-Containment Refueling Water Storage Tank (IRWST). In scenario 3 where the LOCA without ADS stages 1–3 actuations, the depressurization of the primary system is relatively slow and the level of the core coolant drops much earlier than IRWST actuation. In scenario 4 where the accident without ADS stage-4 activation, results in slow depressurization and the level of the core coolant drops earlier than IRWST injection. During the accident process, the core uncovery and fuel heat up did not happen and as a result the safety of AP600 during a 10-in. cold leg MBLOCA was established. The relation between the cladding surface temperature and the primary pressure with the actuation signals of the passive safety systems are compared with that of RELAP5/Mode 3.4 code and a tolerable agreement was obtained.

scholarly journals Modeling The Frontal Collison In Vehicles And Determining The Degree Of Injury On The Driver

2015 ◽  
Vol 67 (1) ◽  
pp. 115-120
Author(s):  
Oana Victoria Oţăt
Keyword(s):  
Dynamic Behaviour ◽  
Research Study ◽  
Research Paper ◽  
Passive Safety ◽  
Steering Wheel ◽  
Passive Safety Systems ◽  
Frontal Collision ◽  
Safety Systems

Abstract The present research study aims at analysing the kinematic and the dynamic behaviour of the vehicle’s driver in a frontal collision. Hence, a subsequent objective of the research paper is to establish the degree of injury suffered by the driver. Therefore, in order to achieve the objectives set, first, we had to define the type of the dummy placed in the position of the driver, and then to design the three-element assembly, i.e. the chair-steering wheel-dashboard assembly. Based on this model, the following step focused on the positioning of the dummy, which has also integrated the defining of the contacts between the components of the dummy and the seat elements. Seeking to model such a behaviour that would highly accurately reflect the driver’s movements in a frontal collision, passive safety systems have also been defined and simulated, namely the seatbelt and the frontal airbag.

scholarly journals Onshore Nuclear Power Plant Concept with Enhanced Passive Safety System

2019 ◽  
Vol 4 (6) ◽  
pp. 155-159
Author(s):  
A.H.M. Iftekharul Ferdous ◽  
T. H. M Sumon Rashid ◽  
Md Asaduzzaman Shobug ◽  
Tanveer Ahmed ◽  
Nitol Kumar Dutta
Keyword(s):  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Water Source ◽  
Passive Safety ◽  
Electric Power Supply ◽  
Passive Safety Systems ◽  
Passive Safety System ◽  
Safety Systems

Bangladesh is a developing country and it’s increasing economy can be maintained by providing sufficient amount of electric power supply. Therefore government is initiating Rooppur nuclear power project is one of them which is needed to be sited beside a vast amount of water source, lowest populated area and away from the locality to reduce the damage caused by any nuclear accidents. In this thesis paper we have shown that, the the dangers of residing errors of Rooppur nuclear power plant and give a proposal to go for onshore nuclear power plant in Bangladesh with two proposed designs of passive safety systems PSS-I & PSS-II. These systems will give safety to the power plants in the case of plant blackout during accidents.

scholarly journals Experiment for Justification the Reliability of Passive Safety System in NPP

2018 ◽  
Vol 3 (3) ◽  
pp. 1
Author(s):  
D.S. Samokhin ◽  
Mohammad Alslman ◽  
A. D. Vostrilova ◽  
O.Yu. Kochnov
Keyword(s):  
Power Systems ◽  
Nuclear Power ◽  
Critical Issue ◽  
Nuclear Industry ◽  
Passive Safety ◽  
Mathematical Methods ◽  
Mean Time Between Failures ◽  
Passive Safety Systems ◽  
Passive Safety System ◽  
Safety Systems

This article gives an overview of the formation of the global nuclear industry, highlighted a critical issue of ensuring safe operation of nuclear power systems in modern projects. Considering the use of passive safety systems in the design of a nuclear power plant, and discussed the different mathematical methods for assessing the reliability of passive systems. Also it considers the possibility of finding the mean time between failures, using these methods to assess the reliability of passive safety systems.

scholarly journals Application of REPAS Methodology to Assess the Reliability of Passive Safety Systems

2009 ◽  
Vol 2009 ◽  
pp. 1-18 ◽  
Author(s):  
Franco Pierro ◽  
Dino Araneo ◽  
Giorgio Galassi ◽  
Francesco D'Auria
Keyword(s):  
Monte Carlo ◽  
Safety Assessment ◽  
Probability Distributions ◽  
Passive Safety ◽  
Passive System ◽  
Passive Systems ◽  
Passive Safety Systems ◽  
Passive Safety System ◽  
Uncertain Input ◽  
Safety Systems

The paper deals with the presentation of the Reliability Evaluation of Passive Safety System (REPAS) methodology developed by University of Pisa. The general objective of the REPAS is to characterize in an analytical way the performance of a passive system in order to increase the confidence toward its operation and to compare the performances of active and passive systems and the performances of different passive systems. The REPAS can be used in the design of the passive safety systems to assess their goodness and to optimize their costs. It may also provide numerical values that can be used in more complex safety assessment studies and it can be seen as a support to Probabilistic Safety Analysis studies. With regard to this, some examples in the application of the methodology are reported in the paper. A best-estimate thermal-hydraulic code, RELAP5, has been used to support the analyses and to model the selected systems. Probability distributions have been assigned to the uncertain input parameters through engineering judgment. Monte Carlo method has been used to propagate uncertainties and Wilks' formula has been taken into account to select sample size. Failure criterions are defined in terms of nonfulfillment of the defined design targets.

scholarly journals The Investigation of Nonavailability of Passive Safety Systems Effects on Small Break LOCA Sequence in AP1000 Using RELAP5 MOD 4.0

2016 ◽  
Vol 2016 ◽  
pp. 1-11 ◽  
Author(s):  
Anwar Hussain ◽  
Amjad Nawaz
Keyword(s):  
Active Region ◽  
Reactor Core ◽  
Passive Safety ◽  
Primary System ◽  
Passive Safety Systems ◽  
Passive Safety System ◽  
Stage 4 ◽  
Loss Of Coolant ◽  
Core Cooling ◽  
Safety Systems

The passive safety systems of AP1000 are designed to operate automatically at desired set-points. However, the unavailability or failure to operate of any of the passive safety systems will change the accident sequence and may affect reactor safety. The analysis in this study is based on some hypothetical scenarios, in which the passive safety system failure is considered during the loss of coolant accidents. Four different cases are assumed, that is, with all passive systems, without actuation of one of the accumulators, without actuation of ADS stages 1–3, and without actuation of ADS stage 4. The actuation of all safety systems at their actuation set-points provides adequate core cooling by injecting sufficient water inventory into reactor core. The LOCA with actuation of one of the accumulators cause early actuation of ADS and IRWST. In case of LOCA without ADS stages 1–3, the primary system depressurization is relatively slow and mixture level above core active region drops much earlier than IRWST actuation. The accident without ADS stage 4 actuation results in slow depressurization and mixture level above core active region drops earlier than IRWST injection. Moreover, the comparison of cladding surface temperature is performed in all cases considered in this work.

Study of Decay Heat Removal Approach for Advanced Passive PWR During Station Blackout

2014 ◽  
Author(s):  
Jie Zou ◽  
Lili Tong ◽  
Xuewu Cao
Keyword(s):  
Cooling System ◽  
Heat Removal ◽  
Safety System ◽  
Injection System ◽  
Passive Safety ◽  
System Failure ◽  
Decay Heat ◽  
Passive Safety Systems ◽  
Station Blackout ◽  
Safety Systems

After Fukushima accident, decay heat removal in station blackout (SBO) accident is concerned for different NPP design. Advanced passive PWR relies on passive systems to cool reactor core and containment, such as the passive residual heat removal system (PRHR), passive injection system and passive containment cooling system (PCCS). Passive safety systems are considered more reliable than traditional active safety system under accident condition. However, in long-term SBO situation, possible failure of passive safety systems is noticed as active valves are needed in system actuation. Moreover, probability safety analysis results of advanced passive PWR show that system failure is possible without external event. Given different passive safety system failure assumptions, response of reactor coolant system and containment of advanced passive PWR is calculated in SBO accident, the integrity of core, reactor pressure vessel and containment is assessed, and decay heat removal approach is studied. The results show that containment failure is predicted with the failure of PCCS and PRHR, reactor vessel failure together with containment failure is predicted with the failure of PCCS, passive injection system and PRHR. Advices to deal with the risk of advanced passive PWR in SBO are given based on the study.

Preliminary Study of Large-Power PWR With Safety Balanced Design

2010 ◽  
Author(s):  
Jue Yang ◽  
Xuenong Zhu ◽  
Xiangang Fu ◽  
Wei Cai ◽  
Jie Ye ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Safety System ◽  
Passive Safety ◽  
Active Safety ◽  
Plant Design ◽  
Large Power ◽  
Passive Safety Systems ◽  
Active Safety Systems ◽  
Environmental Goals ◽  
Safety Systems

Developing the advanced nuclear power plant design to meet the demanding safety, efficiency and environmental goals of electric utilities requires great efforts. In this paper, a design of the safety systems for the large-power PWR units is introduced, which is deemed a optimal combination of the passive safety systems with the active safety systems. The typical design basis accidents are analyzed for this safety system design, such as the Small Break LOCA, SGTR, SLB and Loss of Flow Accidents (LOFA). The results show that the safety systems of the passives combined the actives can mitigate effectively these typical accidents in large-power PWRs. PSA results also show that the passive safety systems contributes to the reduction of the CDF. It is preliminarily concluded that the passive combined active safety system is designed in balance.

Vehicles’ Passive Safety Systems Influence on Driver’s Thorax Injuries

2016 ◽  
Vol 823 ◽  
pp. 187-192 ◽  
Author(s):  
Oana Victoria Oţăt ◽  
Nicolae Dumitru ◽  
Victor Oţăt
Keyword(s):  
Road Traffic ◽  
Seat Belt ◽  
Severity Index ◽  
Passive Safety ◽  
Steering Wheel ◽  
Computer Assisted ◽  
Passive Safety Systems ◽  
Kinematic Behaviour ◽  
Safety Systems ◽  
The Impact

The present underpins a computer-assisted investigation regarding the driver’s behavior and the injuries suffered in frontal vehicle collision, more precisely the injuries suffered in the thorax area. Hence, by means of the LS-Dyna software package we have carried out two series of virtual simulations with a dummy positioned on the driver’s place, i.e. belted and unbelted. For the simulation we have selected a Hybrid III 5th percentile female dummy. Aiming at achieving a simulation that would display a high accuracy degree with respect to the driver’s kinematic behaviour at the impact moment, our complete model also included, besides the dummy, the elements in the habitable: the seat, the seat belt, the steering wheel, the airbag and the dash board. Thus, the focus of the undertaken study was to establish the accelerations in the driver’s thorax area as well as the injury degree, expressed by the CSI (Chest Severity Index). The results obtained validated our hypothesis in that passive safety systems, i.e. the seat belt, diminish considerably the driver’s injuries degree in case of a road traffic accident.

Sign in / Sign up

Export Citation Format

Share Document