Final Report on Accident Tolerant Fuel Performance Analysis of APMT-Steel Clad/UO2 Fuel and APMT-Steel Clad/UN-U3Si5 Fuel Concepts

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ISBN 13 :
Total Pages : pages
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Book Synopsis Final Report on Accident Tolerant Fuel Performance Analysis of APMT-Steel Clad/UO2 Fuel and APMT-Steel Clad/UN-U3Si5 Fuel Concepts by :

Download or read book Final Report on Accident Tolerant Fuel Performance Analysis of APMT-Steel Clad/UO2 Fuel and APMT-Steel Clad/UN-U3Si5 Fuel Concepts written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Severe Accident Scoping Simulations of Accident Tolerant Fuel Concepts for BWRs

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ISBN 13 :
Total Pages : 16 pages
Book Rating : 4.:/5 (925 download)

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Book Synopsis Severe Accident Scoping Simulations of Accident Tolerant Fuel Concepts for BWRs by :

Download or read book Severe Accident Scoping Simulations of Accident Tolerant Fuel Concepts for BWRs written by and published by . This book was released on 2015 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Accident-tolerant fuels (ATFs) are fuels and/or cladding that, in comparison with the standard uranium dioxide Zircaloy system, can tolerate loss of active cooling in the core for a considerably longer time period while maintaining or improving the fuel performance during normal operations [1]. It is important to note that the currently used uranium dioxide Zircaloy fuel system tolerates design basis accidents (and anticipated operational occurrences and normal operation) as prescribed by the US Nuclear Regulatory Commission. Previously, preliminary simulations of the plant response have been performed under a range of accident scenarios using various ATF cladding concepts and fully ceramic microencapsulated fuel. Design basis loss of coolant accidents (LOCAs) and station blackout (SBO) severe accidents were analyzed at Oak Ridge National Laboratory (ORNL) for boiling water reactors (BWRs) [2]. Researchers have investigated the effects of thermal conductivity on design basis accidents [3], investigated silicon carbide (SiC) cladding [4], as well as the effects of ATF concepts on the late stage accident progression [5]. These preliminary analyses were performed to provide initial insight into the possible improvements that ATF concepts could provide and to identify issues with respect to modeling ATF concepts. More recently, preliminary analyses for a range of ATF concepts have been evaluated internationally for LOCA and severe accident scenarios for the Chinese CPR1000 [6] and the South Korean OPR-1000 [7] pressurized water reactors (PWRs). In addition to these scoping studies, a common methodology and set of performance metrics were developed to compare and support prioritizing ATF concepts [8]. A proposed ATF concept is based on iron-chromium-aluminum alloys (FeCrAl) [9]. With respect to enhancing accident tolerance, FeCrAl alloys have substantially slower oxidation kinetics compared to the zirconium alloys typically employed. During a severe accident, FeCrAl would tend to generate heat and hydrogen from oxidation at a slower rate compared to the zirconium-based alloys in use today. The previous study, [2], of the FeCrAl ATF concept during station blackout (SBO) severe accident scenarios in BWRs was based on simulating short term SBO (STSBO), long term SBO (LTSBO), and modified SBO scenarios occurring in a BWR-4 reactor with MARK-I containment. The analysis indicated that FeCrAl had the potential to delay the onset of fuel failure by a few hours depending on the scenario, and it could delay lower head failure by several hours. The analysis demonstrated reduced in-vessel hydrogen production. However, the work was preliminary and was based on limited knowledge of material properties for FeCrAl. Limitations of the MELCOR code were identified for direct use in modeling ATF concepts. This effort used an older version of MELCOR (1.8.5). Since these analyses, the BWR model has been updated for use in MELCOR 1.8.6 [10], and more representative material properties for FeCrAl have been modeled. Sections 2 4 present updated analyses for the FeCrAl ATF concept response during severe accidents in a BWR. The purpose of the study is to estimate the potential gains afforded by the FeCrAl ATF concept during BWR SBO scenarios.

Accident Tolerant Fuel and Cladding Assessment

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ISBN 13 :
Total Pages : pages
Book Rating : 4.:/5 (958 download)

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Book Synopsis Accident Tolerant Fuel and Cladding Assessment by :

Download or read book Accident Tolerant Fuel and Cladding Assessment written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Properties of UO2

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ISBN 13 :
Total Pages : 146 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Properties of UO2 by : J. Belle

Download or read book Properties of UO2 written by J. Belle and published by . This book was released on 1957 with total page 146 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Design-basis Accident Analysis Methods For Light-water Nuclear Power Plants

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Publisher : World Scientific
ISBN 13 : 9813275677
Total Pages : 717 pages
Book Rating : 4.8/5 (132 download)

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Book Synopsis Design-basis Accident Analysis Methods For Light-water Nuclear Power Plants by : Robert Martin

Download or read book Design-basis Accident Analysis Methods For Light-water Nuclear Power Plants written by Robert Martin and published by World Scientific. This book was released on 2019-02-13 with total page 717 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect in a licensing review, historical perspectives and the implication for new designs.This text is an essential resource for practitioners and students, on the current best-practices in nuclear power plant safety and their basis. Contributors of this work are subject matter experts in their specialties, much of which was nurtured and inspired by Prof. Larry Hochreiter, a prominent nuclear safety pioneer.Related Link(s)

Nuclear Fuel Safety Criteria

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Publisher : OECD Publishing
ISBN 13 :
Total Pages : 74 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Nuclear Fuel Safety Criteria by : OECD Nuclear Energy Agency

Download or read book Nuclear Fuel Safety Criteria written by OECD Nuclear Energy Agency and published by OECD Publishing. This book was released on 2001 with total page 74 pages. Available in PDF, EPUB and Kindle. Book excerpt: Presents brief descriptions of 20 fuel-related safety criteria along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them.

Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions

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ISBN 13 : 9789201080202
Total Pages : 218 pages
Book Rating : 4.0/5 (82 download)

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Book Synopsis Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions by : International Atomic Energy Agency

Download or read book Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions written by International Atomic Energy Agency and published by . This book was released on 2020-07-30 with total page 218 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication is the result of an IAEA technical meeting and reports on Member States' capabilities in modelling, predicting and improving their understanding of the behaviour of nuclear fuel under accident conditions. The main results and outcomes of a coordinated research project (CRP) on this topic are also presented.

Deterministic Safety Analysis for Nuclear Power Plants

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Publisher : International Atomic Energy Agency
ISBN 13 : 9789201021199
Total Pages : 85 pages
Book Rating : 4.0/5 (211 download)

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Book Synopsis Deterministic Safety Analysis for Nuclear Power Plants by : International Atomic Energy Agency

Download or read book Deterministic Safety Analysis for Nuclear Power Plants written by International Atomic Energy Agency and published by International Atomic Energy Agency. This book was released on 2019-09-24 with total page 85 pages. Available in PDF, EPUB and Kindle. Book excerpt: Deterministic safety analysis is an essential component of safety assessment, particularly for safety demonstration of the design of nuclear power plants (NPPs). The objective of deterministic safety analysis is to confirm that safety functions can be fulfilled and that the necessary structures, systems and components, in combination with operator actions, are effective in keeping the releases of radioactive material from the plant below acceptable limits. Deterministic safety analysis, supplemented by further specific information and analysis, including probabilistic safety analysis, is also intended to demonstrate that the source term and the potential radiological consequences of different plant states are acceptable, and that the possibility of certain conditions arising that could lead to an early or a large radioactive release can be considered as 'practically eliminated'. The publication has been updated to maintain consistency with current IAEA safety requirements and to reflect lessons from the Fukushima Daiichi accident. It takes into account current practices and experience from deterministic safety analyses for NPPs being performed around the world.

Boiling Water Reactor Plant

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ISBN 13 :
Total Pages : 218 pages
Book Rating : 4.3/5 (129 download)

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Book Synopsis Boiling Water Reactor Plant by : United Engineers & Constructors, inc

Download or read book Boiling Water Reactor Plant written by United Engineers & Constructors, inc and published by . This book was released on 1972 with total page 218 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Thermophysical Properties Database of Materials for Light Water Reactors and Heavy Water Reactors

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Publisher : IAEA
ISBN 13 :
Total Pages : 416 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Thermophysical Properties Database of Materials for Light Water Reactors and Heavy Water Reactors by : International Atomic Energy Agency

Download or read book Thermophysical Properties Database of Materials for Light Water Reactors and Heavy Water Reactors written by International Atomic Energy Agency and published by IAEA. This book was released on 2006 with total page 416 pages. Available in PDF, EPUB and Kindle. Book excerpt: The thermophysical properties database for materials of light water reactors and heavy water reactors described in this technical document was established within the framework of an IAEA Coordinated Research Project. The database is intended to serve as a useful source of information on thermophysical properties data for water cooled reactor analyses. In particular, it aims at achieving improvements in safety and economics of future plants by helping to remove the need for large design margins to account for limitations of data and methods. The database has been developed into an internationally available Internet database (THERPRO) at Hanyang University (Republic of Korea), and now provides various materials properties data and an interactively accessible information resource and communications medium for researchers and engineers.--Publisher's description.

Zirconium in the Nuclear Industry

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Publisher : ASTM International
ISBN 13 : 0803128959
Total Pages : 891 pages
Book Rating : 4.8/5 (31 download)

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Book Synopsis Zirconium in the Nuclear Industry by : Gerry D. Moan

Download or read book Zirconium in the Nuclear Industry written by Gerry D. Moan and published by ASTM International. This book was released on 2002 with total page 891 pages. Available in PDF, EPUB and Kindle. Book excerpt: Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.

Design of the Reactor Core for Nuclear Power Plants

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Publisher : IAEA
ISBN 13 :
Total Pages : 82 pages
Book Rating : 4.3/5 (91 download)

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Book Synopsis Design of the Reactor Core for Nuclear Power Plants by : International Atomic Energy Agency

Download or read book Design of the Reactor Core for Nuclear Power Plants written by International Atomic Energy Agency and published by IAEA. This book was released on 2005 with total page 82 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication makes recommendations concerning safety features for incorporation into the design of the reactor core for a nuclear power plant, taking account of recent developments in the design of the reactor core and including guidance on general and specific design considerations. It supersedes IAEA Safety Series No. 50-SG-D14.