Author: ... IAEAPublisher:
ISBN: 9789201147196
Category : Fast reactors--Safety measures
Languages : en
Pages : 66
Book Description
Treatment of Residual Sodium and Sodium Potassium from Fast Reactors
Author: ... IAEAPublisher:
ISBN: 9789201147196
Category : Fast reactors--Safety measures
Languages : en
Pages : 66
Book Description
Modelling and Simulation of the Source Term for a Sodium Cooled Fast Reactor Under Hypothetical Severe Accident Conditions
Author: International Atomic Energy AgencyPublisher:
ISBN: 9789201353221
Category :
Languages : en
Pages : 0
Book Description
Within the overall objective to support the development of fast reactor technology and to extend the predictive capabilities of existing simulation tools for design and safety analysis, this publication aims to improve the understanding of key phenomena involving radioactive material transport and reduce uncertainties in the estimation of potential releases to the environment. It arises from an IAEA coordinated research project (CRP), launched to perform modelling and simulation of the source term for sodium cooled fast reactors under hypothetical severe accident conditions. The publication presents the results and conclusions of the CRP to verify and validate modelling the in-vessel and in-containment source terms. The technical aspects addressed by the CRP are divided into three main parts: the in-vessel source term estimation, the primary system/containment interface source term estimation and the in-containment phenomenology. This publication documents the models, simulations, results and discussions.
Status of Fast Reactor Research and Technology Development
Author: International Atomic Energy AgencyPublisher:
ISBN: 9781523130191
Category : Fast reactors
Languages : en
Pages : 0
Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
Nuclear Science Abstracts
Author: Energy Research Abstracts
Author: Structural Materials for Heavy Liquid Metal Cooled Fast Reactors
Author: Publisher:
ISBN: 9781523149919
Category : Liquid metal cooled reactors
Languages : en
Pages : 0
Book Description
"The compatibility of structural materials, such as steels with lead and lead-bismuth eutectic, poses a critical challenge in the development of heavy liquid metal (HLM) cooled fast reactors. Factors such as the high temperatures, fast neutron flux and irradiation exposure and corrosiveness provide a severe environment for the materials in these advanced reactor systems. The compatibility of liquid coolant with structural materials is critical for the development of innovative nuclear energy systems. To understand the current status of the research and development in this area as well as to provide a forum to exchange information on structural materials for HLM cooled reactors at the national and international levels, the IAEA organized a technical meeting. This resulted in the current publication which presents the summaries of the technical and the group sessions, conclusions and recommendations, and the papers presented at the event."--Publisher's description.
Liquid Metal Cooled Reactors
Author: International Atomic Energy AgencyPublisher:
ISBN: 9789201079077
Category : Liquid metal cooled reactors
Languages : en
Pages : 0
Book Description
Presents a survey of worldwide experience gained with fast breeder reactor design, development and operation. Coverage includes state of the art of liquid metal fast reactor development; lead-bismuth cooled (LBC) ship reactor operation experience and LBC fast power reactor development; and treatment and disposal of spent sodium.
Design Features and Operating Experience of Experimental Fast Reactors
Author: International Atomic Energy AgencyPublisher:
ISBN: 9789201364104
Category : Science
Languages : en
Pages : 0
Book Description
As a part of the IAEA efforts for knowledge preservation and data retrieval, this publication compiles and documents significant aspects of fast reactor engineering development and experience. Its focus is on research and development activities, experience with experimental facilities, and criteria for comparison liquid metal coolants.
Process Modelling and Simulation
Author: César de PradaPublisher: MDPI
ISBN: 3039214551
Category : Technology & Engineering
Languages : en
Pages : 298
Book Description
Since process models are nowadays ubiquitous in many applications, the challenges and alternatives related to their development, validation, and efficient use have become more apparent. In addition, the massive amounts of both offline and online data available today open the door for new applications and solutions. However, transforming data into useful models and information in the context of the process industry or of bio-systems requires specific approaches and considerations such as new modelling methodologies incorporating the complex, stochastic, hybrid and distributed nature of many processes in particular. The same can be said about the tools and software environments used to describe, code, and solve such models for their further exploitation. Going well beyond mere simulation tools, these advanced tools offer a software suite built around the models, facilitating tasks such as experiment design, parameter estimation, model initialization, validation, analysis, size reduction, discretization, optimization, distributed computation, co-simulation, etc. This Special Issue collects novel developments in these topics in order to address the challenges brought by the use of models in their different facets, and to reflect state of the art developments in methods, tools and industrial applications.
Benchmark Analyses on the Natural Circulation Test Performed During the Phenix End-Of-Life Experiments: IAEA Tecdoc Series
Author: International Atomic Energy AgencyPublisher: International Atomic Energy Agency
ISBN: 9789201396105
Category : Political Science
Languages : en
Pages : 169
Book Description
"This publication is based on the experience of an IAEA coordinated research project on control rod withdrawal and sodium natural circulation tests performed during the Phenix end-of-life experiments. Presented in this publication are the benchmark analyses of the natural circulation test performed before the definite shutdown of the reactor. The experimental data gathered during these tests represent a unique resource to carry out validation analyses and code-to-code comparisons. The benchmark analyses allowed participants to investigate and verify several system and safety codes currently used in the analyses of liquid metal thermal hydraulics phenomena in sodium fast reactors."--Publisher's description.