Iaea Nea Workshop On Best Estimate Methods And Uncertainty Evaluations
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Iaea Nea Workshop On Best Estimate Methods And Uncertainty Evaluations
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Author : AEA-NEA Workshop on best estimate methods and uncertainty evaluations
language : en
Publisher:
Release Date : 2011
Iaea Nea Workshop On Best Estimate Methods And Uncertainty Evaluations written by AEA-NEA Workshop on best estimate methods and uncertainty evaluations and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2011 with categories.
Best Estimate Safety Analysis For Nuclear Power Plants
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Author :
language : en
Publisher:
Release Date : 2008
Best Estimate Safety Analysis For Nuclear Power Plants written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2008 with Business & Economics categories.
Deterministic safety analysis is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants (NPPs). IAEA Safety Standards Series No. NS-R-1.2 and Safety Reports Series No. 23 recommend, as one of the options for demonstrating the inclusion of adequate safety margins, the use of best estimate computer codes with realistic input data in combination with the evaluation of uncertainties in the calculation results. The evaluation of uncertainties is an issue of considerable complexity, and this Safety Report has been developed to complement the existing publications. It provides more detailed information on the methods available for the evaluation of uncertainties in deterministic safety analysis of NPPs and practical guidance in the use of these methods.
Deterministic Best Estimate Safety Analysis Including Uncertainties
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Author : Nenad Debrecin
language : en
Publisher:
Release Date : 2006
Deterministic Best Estimate Safety Analysis Including Uncertainties written by Nenad Debrecin and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2006 with categories.
Methodologies For Seismic Safety Evaluation Of Existing Nuclear Installations
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Author : IAEA
language : en
Publisher: International Atomic Energy Agency
Release Date : 2020-08-26
Methodologies For Seismic Safety Evaluation Of Existing Nuclear Installations written by IAEA and has been published by International Atomic Energy Agency this book supported file pdf, txt, epub, kindle and other format this book has been release on 2020-08-26 with Technology & Engineering categories.
Experience shows that an assessment of the seismic capacity of an existing operating facility can be required for a number of reasons, for example identification of potential seismic vulnerabilities based on operating experience events or the periodic safety review programme. This publication covers the seismic safety evaluation programmes to be performed on existing nuclear installations in order to ensure that the required fundamental safety functions are available, with particular attention to the safe shutdown of reactors. It includes lessons learned based on the IAEA Action Plan on Nuclear Safety following the Fukushima Daiichi accident, and updated methodologies for seismic safety evaluation of nuclear installations.
Thermal Hydraulics Of Water Cooled Nuclear Reactors
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Author : Francesco D'Auria
language : en
Publisher: Woodhead Publishing
Release Date : 2017-05-18
Thermal Hydraulics Of Water Cooled Nuclear Reactors written by Francesco D'Auria and has been published by Woodhead Publishing this book supported file pdf, txt, epub, kindle and other format this book has been release on 2017-05-18 with Technology & Engineering categories.
Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants
Quality And Reliability Aspects In Nuclear Power Reactor Fuel Engineering
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Author : IAEA
language : en
Publisher: International Atomic Energy Agency
Release Date : 2024-02-20
Quality And Reliability Aspects In Nuclear Power Reactor Fuel Engineering written by IAEA and has been published by International Atomic Energy Agency this book supported file pdf, txt, epub, kindle and other format this book has been release on 2024-02-20 with Technology & Engineering categories.
Improved fuel reliability means reduced fuel failures in reactor operation. Fuel failures, with their consequent adverse impact on the environment and requirements for additional waste management, result in costs for remediation, 'failed core' operation and maintenance. Therefore, poor performance of fuel can lead to uncompetitive operational conditions for a nuclear power plant. A revision of the earlier edition, this publication has been significantly extended to support nuclear fuel designers, manufacturers, reactor operators, and fuel engineers and managers on fuel design and design changes, fuel manufacturing, qualification, in-reactor operation, and on-site services to achieve excellence in fuel reliability and performance and safe operation of nuclear fuel under all applicable plant states.
Safety Margins Of Operating Rectors
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Author : M. Antila
language : en
Publisher: International Atomic Energy Agency
Release Date : 2003
Safety Margins Of Operating Rectors written by M. Antila and has been published by International Atomic Energy Agency this book supported file pdf, txt, epub, kindle and other format this book has been release on 2003 with Business & Economics categories.
This TECDOC deals with a basic concept of safety margins and their role in assuring safety of nuclear Installations. The document describes capabilities of thermal hydraulic computer codes used to determine safety margins, evaluation of uncertainties, methods for safety margin evaluation and utilization of safety margins in operation and modifications of nuclear power plants.
The Iaea Coordinated Research Program On Htgr Uncertainty Analysis
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Author :
language : en
Publisher:
Release Date : 2014
The Iaea Coordinated Research Program On Htgr Uncertainty Analysis written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2014 with categories.
The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of HTGR design and safety features with reliable high fidelity physics models and robust, efficient, and accurate codes. One way to address the uncertainties in the HTGR analysis tools are to assess the sensitivity of critical parameters (such as the calculated maximum fuel temperature during loss of coolant accidents) to a few important input uncertainties. The input parameters were identified by engineering judgement in the past but are today typically based on a Phenomena Identification Ranking Table (PIRT) process. The input parameters can also be derived from sensitivity studies and are then varied in the analysis to find a spread in the parameter of importance. However, there is often no easy way to compensate for these uncertainties. In engineering system design, a common approach for addressing performance uncertainties is to add compensating margins to the system, but with passive properties credited it is not so clear how to apply it in the case of modular HTGR heat removal path. Other more sophisticated uncertainty modelling approaches, including Monte Carlo analysis, have also been proposed and applied. Ideally one wishes to apply a more fundamental approach to determine the predictive capability and accuracies of coupled neutronics/thermal-hydraulics and depletion simulations used for reactor design and safety assessment. Today there is a broader acceptance of the use of uncertainty analysis even in safety studies and it has been accepted by regulators in some cases to replace the traditional conservative analysis. Therefore some safety analysis calculations may use a mixture of these approaches for different parameters depending upon the particular requirements of the analysis problem involved. Sensitivity analysis can for example be used to provide information as part of an uncertainty analysis to determine best estimate plus uncertainty results to the required confidence level. In order to address uncertainty propagation in analysis and methods in the HTGR community the IAEA initiated a Coordinated Research Project (CRP) on the HTGR Uncertainty Analysis in Modelling (UAM) [6] that officially started in 2013. Although this project focuses specifically on the peculiarities of HTGR designs and its simulation requirements, many lessons can be learned from the LWR community and the significant progress already made towards a consistent methodology uncertainty analysis. In the case of LWRs the NRC has already in 1988 amended 10 CFR 50.46 to allow best-estimate (plus uncertainties) calculations of emergency core cooling system performance. The Nuclear Energy Agency (NEA) of the Organization for Economic Co-operation and Development (OECD) also established an Expert Group on "Uncertainty Analysis in Modelling" which finally led to the definition of the "Benchmark for Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of LWRs" [7]. The CRP on HTGR UAM will follow as far as possible the on-going OECD Light Water Reactor UAM benchmark activity.
International Structure For Decommissioning Costing Isdc Of Nuclear Installations
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Author : Organisation de coopération et de développement économiques
language : en
Publisher:
Release Date : 2012
International Structure For Decommissioning Costing Isdc Of Nuclear Installations written by Organisation de coopération et de développement économiques and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2012 with Nuclear energy categories.
Cost estimation for the decommissioning of nuclear facilities can vary considerably in format, content and practice both within and across countries. These differences may have legitimate reasons but make the process of reviewing estimates complicated and the estimates themselves difficult to defend. Hence, the joint initiative of the OECD Nuclear Energy Agency (NEA), the International Atomic Energy Agency (IAEA) and the European Commission (EC) was undertaken to propose a standard itemisation of decommissioning costs either directly for the production of cost estimates or for mapping estimates onto a standard, common structure for purposes of comparison. This report updates the earlier itemisation published in 1999 and takes into account experience accumulated thus far. The revised cost itemisation structure has sought to ensure that all costs within the planned scope of a decommissioning project may be reflected. The report also provides general guidance on developing a decommissioning cost estimate, including detailed advice on using the structure.
The Iaea Coordinated Research Program On Htgr Reactor Physics Thermal Hydraulics And Depletion Uncertainty Analysis
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Author :
language : en
Publisher:
Release Date : 2012
The Iaea Coordinated Research Program On Htgr Reactor Physics Thermal Hydraulics And Depletion Uncertainty Analysis written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2012 with categories.
The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of design and safety features with reliable high fidelity physics models and robust, efficient, and accurate codes. The uncertainties in the HTR analysis tools are today typically assessed with sensitivity analysis and then a few important input uncertainties (typically based on a PIRT process) are varied in the analysis to find a spread in the parameter of importance. However, one wish to apply a more fundamental approach to determine the predictive capability and accuracies of coupled neutronics/thermal-hydraulics and depletion simulations used for reactor design and safety assessment. Today there is a broader acceptance of the use of uncertainty analysis even in safety studies and it has been accepted by regulators in some cases to replace the traditional conservative analysis. Finally, there is also a renewed focus in supplying reliable covariance data (nuclear data uncertainties) that can then be used in uncertainty methods. Uncertainty and sensitivity studies are therefore becoming an essential component of any significant effort in data and simulation improvement. In order to address uncertainty in analysis and methods in the HTGR community the IAEA launched a Coordinated Research Project (CRP) on the HTGR Uncertainty Analysis in Modelling early in 2012. The project is built on the experience of the OECD/NEA Light Water Reactor (LWR) Uncertainty Analysis in Best-Estimate Modelling (UAM) benchmark activity, but focuses specifically on the peculiarities of HTGR designs and its simulation requirements. Two benchmark problems were defined with the prismatic type design represented by the MHTGR-350 design from General Atomics (GA) while a 250 MW modular pebble bed design, similar to the INET (China) and indirect-cycle PBMR (South Africa) designs are also included. In the paper more detail on the benchmark cases, the different specific phases and tasks and the latest status and plans are presented.