scholarly journals Uncertainty Analysis of Method-Based Operating Event Groups Ranking

2014 ◽  
Vol 2014 ◽  
pp. 1-12 ◽  
Author(s):  
Zdenko Šimić ◽  
Benoit Zerger ◽  
Reni Banov

Safe operation and industrial improvements are coming from the technology development and operational experience (OE) feedback. A long life span for many industrial facilities makes OE very important. Proper assessment and understanding of OE remains a challenge because of organization system relations, complexity, and number of OE events acquired. One way to improve OE events understanding is to focus their investigation and analyze in detail the most important. The OE ranking method is developed to select the most important events based on the basic event parameters and the analytical hierarchy process applied at the level of event groups. This paper investigates further how uncertainty in the model affects ranking results. An analysis was performed on the set of the two databases from the 20 years of nuclear power plants in France and Germany. From all uncertainties the presented analysis selected ranking indexes as the most relevant for consideration. Here the presented analysis of uncertainty clearly shows that considering uncertainty is important for all results, especially for event groups ranked closely and next to the most important one. Together with the previously performed sensitivity analysis, uncertainty assessment provides additional insights and a better judgment of the event groups’ importance in further detailed investigation.

Author(s):  
Holger Schmidt ◽  
Martin Betz ◽  
Ingo Ganzmann ◽  
Achim Beisiegel ◽  
Thomas Wagner ◽  
...  

Atomic Energy ◽  
2006 ◽  
Vol 101 (2) ◽  
pp. 539-543 ◽  
Author(s):  
Yu. G. Dragunov ◽  
V. P. Denisov

Author(s):  
C. Baroux ◽  
M. Detrilleaux ◽  
G. Demazy

Abstract Spent nuclear fuel has been stored at the DOEL power station in Belgium in dual-purpose metal casks since 1995. The casks were procured from TRANSNUCLEAIRE by SYNATOM to meet the operational demands for on-site dry storage solutions for fuel arising from the four PWR reactors at DOEL. The TN 24 type of cask was chosen and a range of different cask types were developed. The initial requirement was for dual purpose cask to contain fuel from the DOEL units 3 and 4, these having similar fuel types but different lengths, and thus two new members of the TN 24 family were developed; the TN 24 D and TN 24 XL with capacities of 28 and 24 SFA’s. These casks were licensed as B(U) fissile packagings with approval certificates granted by the French and validated by the Belgium competent authorities for the transport configurations. Both cask designs were also analyzed by TRANSNUCLEAIRE in their storage configurations to ensure that the criteria for safe interim storage could be met. Since 1995, a total of 18 TN 24 D and TN 24 XL casks have been loaded with spent fuel assemblies with an average burn-up of 40,000 MWd/tU. SYNATOM subsequently decided to purchase further casks for DOEL 3 and 4 fuels with higher enrichments, higher burn-ups and shorter cooling times. TRANSNUCLEAIRE developed the TN 24 DH and TN 24 XLH casks within the similar envelope size and weight limits. The increase in performance was achieved by an in-depth optimization of each design in terms of radiation shielding, heat transfer and criticality safety. This paper shows how this optimization process was undertaken for the TN 24 DH and TN 24 XLH casks, 16 of which have been ordered by SYNATOM. DOEL 1 and 2 units use much shorter PWR fuel and it was decided to ship the fuel to unit 3 with an internal transfer cask because the handling limitations in the DOEL 1 and 2 pool prohibited the loading of a high capacity dual purpose transport/storage cask. The TN 24 SH cask was subsequently designed for DOEL 1 and 2 PWR fuel with a capacity of 37 assemblies and nine of there casks have been ordered by SYNATOM. The casks are fitted with monitoring devices to detect any change in the performance of the double metal O ring closure system and none of the casks has shown any deterioration in leaktightness. This paper examines the operation experience of loading and storing more than 30 TN 24 dual purpose casks and compares the performance with design expectations.


2016 ◽  
Vol 184 (4) ◽  
pp. 575-583 ◽  
Author(s):  
Antonio Ballesteros ◽  
Radian Sanda ◽  
Michael Maqua ◽  
Jean-Luc Stephan

Author(s):  
Balhassn S. M. Ali

Most of the large components in the thermal, traditional and nuclear power plants such as pressurized vessels and pipes are operating at elevated temperatures. These temperatures and stress are high enough for creep to occur. For variety of reasons many of these power plants are now operating beyond their design life time. It is -known fact that as the high temperature components aged the failure rate normally increases as a result of their time dependent material damage. Further running of these components may become un-safe and dangerous in some cases. Therefore, creep assessment of the high temperature components of these plants is essential for their safe operation. Mainly for economic reasons these components have to be creep assessed as they are in service. However, assessing the creep strength for these high temperature components as they are in service, it can be challenging task, especially when these components are operating under extremely high temperature and/or stress. This paper introduces newly invented, small creep test specimens techniques. These new small types of specimens can be used to assess the remaining life times for the high temperature components, using only small material samples. These small material samples can be removed from the operating components surface, without affecting their safe operation. Two of the high temperature materials are used to validate the new testing techniques.


2021 ◽  
Author(s):  
Sam Sadeghi

Safety is the most important aspect and is considered the overwriting priority in nuclear power plants, which comprise of thousands of systems and components that work systematically together for the purpose of generating electricity in a safe, economical and environmentally friendly manner. As the instrumentation and electrical components advance and become more sophisticated and migrate from analog design to the more complicated and error-prone software-based topology, the task of determining that a programmable electronic system (PES) is capable of meeting its safety-related design objective becomes ever more challenging. The dependence on the PES to accomplish its safety-related object must be thoroughly studied to assess the safety-related impacts associated with the potential failure modes of the device. Application Specific Product Qualification (ASPQ) is used to provide neccessay aasurance in the design integrity of a PES and confirms that the product can meet the requirements of a safety-related application. This report is an application specific product qualification (ASPQ) assessment of WEP 1010-110/120-NEA and WEP 1020-110/120-NEA Uninterruptible Power Supplies manufactured by Gambit Electronic Ltd. Information referenced in this report is based on the data received from Gambit, other nuclear power plants using Gambit products and the site visit paid to Gambit, Country-X in August 2007. Gambit WEP 1010- and 10XX-XXX/YY NEA UPS systems are used to provide uninterruptible Class II power to a number of safety-related control and instrumentation power distribution panels for R1 and R2 reactors located in X facility. These UPS are commercial Off-the Shelf (COTS) products intended for industrial uninterruptible power supply applications. An earlier Categorization Assessment Report concluded that UPS perform Category B safety-related functions and therefore, they must be qualified to meet the safety requirements associated with a Class BProgrammable Electronic System (PES) as per IEC 61513.A combination of methods were utilized to demonstrate that the UPS systems were suitable for the target applications, were inherently correct in design, and came with sufficient documentation to allow safe operation by the plant. The key findings of this report indicate that the aforementioned UPS systems are suitable for use in the target application, have strong evidence of reliability through field experience and various product certifications that support correctness of their design and come with thorough documentation that support safe operation and suitability assessment. Two major recommendations made in this report are to establishing a Preventive Maintenance (PM) program by the station to perform replacement of life-limiting components at the minimum frequencies specified by the manufacturerer, and to set ip an inspection and testing program by the station to perform minimum -monthly testing of the output power quality of the UPS systems to minimize the possibility of partial failure, which is the failure of concern and relates to a situation where the loads are supplied with out-of-specification power, undetected.


2017 ◽  
Vol 75 ◽  
pp. 1198-1206 ◽  
Author(s):  
Mostafa Azizkhani ◽  
Abdullah Vakili ◽  
Younes Noorollahi ◽  
Farzin Naseri

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