Advanced Reactor Safety Research Quarterly Report, January-March 1982 PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Advanced Reactor Safety Research Quarterly Report, January-March 1982 PDF full book. Access full book title Advanced Reactor Safety Research Quarterly Report, January-March 1982 by U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research. Download full books in PDF and EPUB format.
Author: U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research
Publisher:
ISBN:
Category : Liquid metal fast breeder reactors
Languages : en
Pages :
Get Book Here
Book Description
Author: U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research
Publisher:
ISBN:
Category : Liquid metal fast breeder reactors
Languages : en
Pages :
Get Book Here
Book Description
Author: Sandia National Laboratories. Advanced Reactor Research Department
Publisher:
ISBN:
Category : Pressurized water reactors
Languages : en
Pages : 460
Get Book Here
Book Description
Author: Sandia National Laboratories
Publisher:
ISBN:
Category : Liquid metal fast breeder reactors
Languages : en
Pages : 312
Get Book Here
Book Description
Author: U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research
Publisher:
ISBN:
Category : Liquid metal fast breeder reactors
Languages : en
Pages :
Get Book Here
Book Description
Author: U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research
Publisher:
ISBN:
Category : Liquid metal fast breeder reactors
Languages : en
Pages :
Get Book Here
Book Description
Author: Sandia National Laboratories
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 184
Get Book Here
Book Description
Author: Sandia National Laboratories
Publisher:
ISBN:
Category : Light water reactors
Languages : en
Pages : 176
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
This report describes progress in a number of activities dealing with current safety issues relevant to both light water reactors (LWRs) and breeder reactors. The work includes a broad range of experiments to simulate accidental conditions to provide the required data base to understand important accident sequences and to serve as a basis for development and verification of the complex computer simulation models and codes used in accident analysis and licensing reviews. Such a program must include the development of analytical models, verified by experiment, which can be used to predict reactor and safety system performance under a broad variety of abnormal conditions. Current major emphasis is focused on providing information to NRC relevant to (1) its deliberations and decisions dealing with severe LWR accidents and (2) its safety evaluation of the proposed Clinch River Breeder Reactor.
Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 654
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Get Book Here
Book Description
This document summarizes work performed by Pacific Northwest Laboratory (PNL) from January 1 through March 31, 1982, for the Division of Accident Evaluation and the Division of Engineering Technology, US Nuclear Regulatory Commission (NRC). Evaluations of nondestructive examination (NDE) techniques and instrumentation are reported; areas of investigation include demonstrating the feasibility of determining the strength of structural graphite, evaluating the feasibility of detecting and analyzing flaw growth in reactor pressure boundary systems, examining NDE reliability and probabilistic fracture mechanics, and assessing the integrity of pressurized water reactor (PWR) steam generator tubes where service-induced degradation has been indicated. Experimental data and analytical models are being provided to aid in decision-making regarding pipe-to-pipe impacts following postulated breaks in high-energy fluid system piping. Core thermal models are being developed to provide better digital codes to compute the behavior of full-scale reactor systems under postulated accident conditions. Fuel assemblies and analytical support are being provided for experimental programs at other facilities.
