Review of Reactor Safety Analyses of Fast and Liquid Metal Cooled Reactors
Title | Review of Reactor Safety Analyses of Fast and Liquid Metal Cooled Reactors PDF eBook |
Author | R. E. Shaver |
Publisher | |
Pages | 58 |
Release | 1967 |
Genre | |
ISBN |
Small Liquid Metal Cooled Reactor Safety Study
Title | Small Liquid Metal Cooled Reactor Safety Study PDF eBook |
Author | N. Brown |
Publisher | |
Pages | 63 |
Release | 2005 |
Genre | |
ISBN |
The Small Liquid Metal Cooled Reactor Safety Study documents results from activities conducted under Small Liquid Metal Fast Reactor Coordination Program (SLMFR-CP) Agreement, January 2004, between the Central Research Institute of the Electric Power Industry (CRIEPI) of Japan and the Lawrence Livermore National Laboratory (LLNL)[1]. Evaluations were completed on topics that are important to the safety of small sodium cooled and lead alloy cooled reactors. CRIEPI investigated approaches for evaluating postulated severe accidents using the CANIS computer code. The methods being developed are improvements on codes such as SAS 4A used in the US to analyze sodium cooled reactors and they depend on calibration using safety testing of metal fuel that has been completed in the TREAT facility. The 4S and the small lead cooled reactors in the US are being designed to preclude core disruption from all mechanistic scenarios, including selected unprotected transients. However, postulated core disruption is being evaluated to support the risk analysis. Argonne National Laboratory and the University of California Berkeley also supported LLNL with evaluation of cores with small positive void worth and core designs that would limit void worth. Assessments were also completed for lead cooled reactors in the following areas: (1) continuing operations with cladding failure, (2) large bubbles passing through the core and (3) recommendations concerning reflector control. The design approach used in the US emphasizes reducing the reactivity in the control mechanisms with core designs that have essentially no, or a very small, reactivity change over the core life. This leads to some positive void worth in the core that is not considered to be safety problem because of the inability to identify scenarios that would lead to voiding of lead. It is also believed that the void worth will not dominate the severe accident analysis. The approach used by 4S requires negative void worth throughout the core life, which leads to large reactivity worth in the control systems. The conclusions from the evaluations support the high level of safety that can be achieved with small liquid metal cooled reactors using either approach.
Safety of Sodium-Cooled Fast Reactors
Title | Safety of Sodium-Cooled Fast Reactors PDF eBook |
Author | Songbai Cheng |
Publisher | Springer Nature |
Pages | 313 |
Release | 2021-09-27 |
Genre | Science |
ISBN | 9811661162 |
This book highlights the advances and trends in the safety analysis of sodium-cooled fast reactors, especially from the perspective of particle bed-related phenomena during core disruptive accidents. A sodium-cooled fast reactor (SFR) is an optimized candidate of the next-generation nuclear reactor systems. Its safety is a critical issue during its R&D process. The book elaborates on research progresses in particle bed-related phenomena in terms of the molten-pool mobility, the molten-pool sloshing motion, the debris bed formation behavior, and the debris bed self-leveling behavior. The book serves as a good reference for researchers, professionals, and postgraduate students interested in sodium-cooled fast reactors. Knowledge provided is also useful for those who are engaging in severe accident analysis for lead-cooled fast reactors and light water reactors.
Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
Title | Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors PDF eBook |
Author | Ferry Roelofs |
Publisher | Woodhead Publishing |
Pages | 464 |
Release | 2018-11-30 |
Genre | Science |
ISBN | 0081019815 |
Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge. - Presents the latest information on one of the deliverables of the SESAME H2020 project - Provides an overview on the design and history of liquid metal cooled fast reactors worldwide - Describes the challenges in thermal hydraulics related to the design and safety analysis of liquid metal cooled fast reactors - Includes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor thermal hydraulic simulations clearly - Discusses state-of-the-art, multi-scale techniques for liquid metal fast reactor thermal hydraulics applications
Fast Reactor Safety
Title | Fast Reactor Safety PDF eBook |
Author | John Graham |
Publisher | Elsevier |
Pages | 390 |
Release | 2012-12-02 |
Genre | Technology & Engineering |
ISBN | 0323152651 |
Fast Reactor Safety deals with safety design criteria and methodology for fast reactors. Topics covered include safety evaluation methods, system disturbances, containment, and licensing. The characteristics of fast reactors, including heat ratings and coolants, are also discussed. Comprised of six chapters, this book opens with an overview of methods used to evaluate nuclear safety, along with neutron kinetics, thermal and feedback effects, and fault tree analysis. The reader is then introduced to possible system disturbances in relation to three distinct fast reactor systems: liquid-metal-cooled fast breeder reactors, gas-cooled fast breeder reactors, and steam-cooled fast breeder reactors. The next chapter looks at safety criteria that are set to define the design of a safe plant, together with the safety features that might be included. The remaining chapters focus on the particular problems of a sodium-cooled design; containment building and primary circuit and vessel containment; and licensing of the plant. This monograph is intended for graduates and undergraduates in nuclear engineering who are attending courses in reactor safety.
Liquid Metal Cooled Reactors
Title | Liquid Metal Cooled Reactors PDF eBook |
Author | International Atomic Energy Agency |
Publisher | |
Pages | 0 |
Release | 2007 |
Genre | Liquid metal cooled reactors |
ISBN | 9789201079077 |
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.
Safety Problems of Liquid-metal-cooled Fast Breeder Reactors
Title | Safety Problems of Liquid-metal-cooled Fast Breeder Reactors PDF eBook |
Author | C. N. Kelber |
Publisher | |
Pages | 220 |
Release | 1970 |
Genre | Liquid metal cooled reactors |
ISBN |