Advancing the State of the Practice in Uncertainty and Sensitivity Methodologies for Severe Accident Analysis in Water Cooled Reactors of CANDU Types PDF Download
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Author: IAEA Publisher: ISBN: 9789201220240 Category : Languages : en Pages : 0
Book Description
The IAEA facilitated collaborative research among its Member States, in advancing the state of the practice in uncertainty and sensitivity methodologies for severe accident analysis in water cooled reactors. The primary aim was to evaluate the uncertainty and sensitivity associated with severe accident calculations, particularly concerning the progression and consequences of accidents in a generic CANDU type nuclear power plant under a postulated station blackout scenario. Key parameters considered in these analyses included hydrogen generation, event timings, and the release of fission products into the environment. The resulting publication showcases contributions from three institutions across three Member States, providing insights into their methodologies for uncertainty and sensitivity analysis in severe accidents.
Author: IAEA Publisher: ISBN: 9789201220240 Category : Languages : en Pages : 0
Book Description
The IAEA facilitated collaborative research among its Member States, in advancing the state of the practice in uncertainty and sensitivity methodologies for severe accident analysis in water cooled reactors. The primary aim was to evaluate the uncertainty and sensitivity associated with severe accident calculations, particularly concerning the progression and consequences of accidents in a generic CANDU type nuclear power plant under a postulated station blackout scenario. Key parameters considered in these analyses included hydrogen generation, event timings, and the release of fission products into the environment. The resulting publication showcases contributions from three institutions across three Member States, providing insights into their methodologies for uncertainty and sensitivity analysis in severe accidents.
Author: International Atomic Energy Agency Publisher: ISBN: 9789201274106 Category : Science Languages : en Pages : 423
Book Description
Based on an IAEA coordinated research project focused on the use of passive safety systems and natural circulation to help meet the safety and economic goals of advanced nuclear power plants, this publication includes the identification and definition of the thermo-hydraulic phenomena that affect the reliability of passive safety systems, characterization of each phenomenon, integral tests to examine the passive systems and natural circulation, and a methodology for examining passive system reliability.
Author: International Atomic Energy Agency Publisher: International Atomic Energy Agency ISBN: 9789201019196 Category : Technology & Engineering Languages : en Pages : 74
Book Description
There is considerable interest in both developing and developed countries in the design of innovative water cooled reactors (WCRs) and, owing to the higher thermal efficiency and significant system simplifications, supercritical water cooled reactors (SWCRs). Compared to conventional WCRs the SCWR concept requires extensive, comprehensive research and development (R&D). Fundamental research in understanding important phenomena has been completed successfully in providing information required for the next step of development. Currently, a few concepts have been assessed as being technical feasible, and several other concepts are under development. These concepts are described in this publication, together with detailed analysis of remaining gaps requiring future R&D.
Author: IAEA. Publisher: ISBN: 9789201538178 Category : Electronic books Languages : en Pages : 0
Book Description
One of the most important lessons from the accident at the Fukushima Daiichi nuclear power plant is that a reliable containment venting system can be crucial for effective accident management during severe accidents, especially for smaller volume containments in relation to the rated nuclear power. Containment venting can enhance the capability to maintain core cooling and containment integrity as well as reduce uncontrolled radioactive releases to the environment if the venting system has a filtration capacity. In general, a filtered containment vent system increases the flexibility of plant personnel in coping with unforeseen events. This publication provides the overview of the current status of related activities with the goal to share information between Member States on actions, upgrades, and new technologies pertaining to containment cooling and venting.
Author: International Atomic Energy Agency Publisher: IAEA ISBN: Category : Business & Economics Languages : en Pages : 656
Book Description
Describes the state of knowledge of natural circulation in water cooled nuclear power plants and passive system reliability. The publication presents information on phenomena, models, predictive tools and experiments that currently support design and analysis of natural circulation systems, and highlights areas where additional research is needed.
Author: International Atomic Energy Agency Publisher: ISBN: 9789201043191 Category : Business & Economics Languages : en Pages : 65
Book Description
This updated version of Nuclear Energy Series NF-T-2.1 provides information on all aspects of fuel failures in current nuclear power plant operations.
Author: Publisher: ISBN: Category : Business & Economics Languages : en Pages : 216
Book Description
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.
Author: International Atomic Energy Agency Publisher: ISBN: 9789201022103 Category : Technology & Engineering Languages : en Pages : 0
Book Description
The objective of this Safety Guide is to provide recommendations for meeting the IAEA safety requirements in performing or managing a level 2 probabilistic safety assessment (PSA) project for a nuclear power plant; thus it complements the Safety Guide on level 1 PSA. One of the aims of this Safety Guide is to promote a standard framework, standard terms and a standard set of documents for level 2 PSAs to facilitate regulatory and external peer review of their results. It describes all elements of the level 2 PSA that need to be carried out if the starting point is a fully comprehensive level 1 PSA. Contents: 1. Introduction; 2. PSA project management and organization; 3. Identification of design aspects important to severe accidents and acquisition of information; 4. Interface with level 1 PSA: Grouping of sequences; 5. Accident progression and containment analysis; 6. Source terms for severe accidents; 7. Documentation of the analysis: Presentation and interpretation of results; 8. Use and applications of the PSA; References; Annex I: Example of a typical schedule for a level 2 PSA; Annex II: Computer codes for simulation of severe accidents; Annex III: Sample outline of documentation for a level 2 PSA study.
Author: International Atomic Energy Agency Publisher: International Atomic Energy Agency ISBN: 9789201029195 Category : Technology & Engineering Languages : en Pages : 96
Book Description
Accurate prediction of source term and modelling of severe accident progression by severe accident analysis codes is integral to the safe operation of water cooled reactors in both developing and developed Member States. The source term released to the environment during severe accidents, calculated by these codes, is utilized by specialized atmospheric transport codes to evaluate the transport of radionuclides in the environment. Though severe accident codes are comprehensively validated based on experiments, there remains disagreement among calculations performed using different codes for the same scenarios. Such differences and their causes are being explored by a number of organizations, including cooperation by developers through code to code benchmarks. Furthermore, severe accident phenomena model improvements are being made with insights from experiments and with the development of models to account for previously less understood phenomena. This publication summarizes the current status of severe accident analysis codes and recommends areas for research and development. The information is detailed in terms of major findings, identified gaps, and recommended future actions.
Author: IAEA
Author: IAEA
Author: IAEA.
Author: International Atomic Energy Agency
Author: International Atomic Energy Agency
Author: IAEA.
Author: International Atomic Energy Agency
Author: International Atomic Energy Agency
Author: 
Author: International Atomic Energy Agency
Author: International Atomic Energy Agency