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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Nuclear Fuel Safety Criteria
Author | : OECD Nuclear Energy Agency |
Publisher | : OECD Publishing |
Total Pages | : 74 |
Release | : 2001 |
Genre | : Technology & Engineering |
ISBN | : |
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.
Design-basis Accident Analysis Methods For Light-water Nuclear Power Plants
Author | : Robert Martin |
Publisher | : World Scientific |
Total Pages | : 717 |
Release | : 2019-02-13 |
Genre | : Technology & Engineering |
ISBN | : 9813275677 |
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)
Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions
Author | : International Atomic Energy Agency |
Publisher | : |
Total Pages | : 218 |
Release | : 2020-07-30 |
Genre | : |
ISBN | : 9789201080202 |
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.
Boiling Water Reactor Plant
Author | : United Engineers & Constructors, inc |
Publisher | : |
Total Pages | : 218 |
Release | : 1972 |
Genre | : Boiling water reactors |
ISBN | : |
Deterministic Safety Analysis for Nuclear Power Plants
Author | : International Atomic Energy Agency |
Publisher | : International Atomic Energy Agency |
Total Pages | : 85 |
Release | : 2019-09-24 |
Genre | : Technology & Engineering |
ISBN | : 9789201021199 |
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.
Thermophysical Properties Database of Materials for Light Water Reactors and Heavy Water Reactors
Author | : International Atomic Energy Agency |
Publisher | : IAEA |
Total Pages | : 416 |
Release | : 2006 |
Genre | : Business & Economics |
ISBN | : |
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
Author | : Gerry D. Moan |
Publisher | : ASTM International |
Total Pages | : 891 |
Release | : 2002 |
Genre | : Nuclear fuel claddings |
ISBN | : 0803128959 |
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
Author | : International Atomic Energy Agency |
Publisher | : IAEA |
Total Pages | : 82 |
Release | : 2005 |
Genre | : Business & Economics |
ISBN | : |
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.