Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 90
Book Description
Nondestructive Evaluation of Monolithic Transportation Casks for Spent Nuclear Fuel
Author: Energy Research Abstracts
Author: Publications of the National Institute of Standards and Technology ... Catalog
Author: National Institute of Standards and Technology (U.S.)Publisher:
ISBN:
Category :
Languages : en
Pages : 406
Book Description
Nondestructive Evaluation of LWR Spent Fuel Shipping Casks
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
An analysis of nondestructive testing (NDT) methods currently being used to evaluate the integrity of Light Water Reactor (LWR) spent fuel shipping casks is presented. An assessment of anticipated NDT needs related to breeder reactor cask requirements is included. Specific R and D approaches to probable NDT problem areas such as the evaluation of austenitic stainless steel weldments are outlined.
Publications of the National Bureau of Standards ... Catalog
Author: United States. National Bureau of StandardsPublisher:
ISBN:
Category :
Languages : en
Pages : 404
Book Description
Nondestructive Evaluation of the VSC-17 Cask
Author: Cecilia HoffmanPublisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
In 2003, representatives from the Central Research Institute of Electric Power Industry (CRIEPI) requested development of a project with the objective of determining the performance of a concrete spent nuclear fuel storage cask. Radiation and environmental effects may cause chemical alteration of the concrete that could result in excessive cracking, spalling, and loss of compressive strength. The Idaho National Laboratory (INL) project team and CRIEPI representatives identified the Ventilated Storage Cask (VSC 17) spent nuclear fuel storage cask, originally located at the INL Test Area North, as a candidate to study cask performance because it had been used to store fuel as part of a dry cask storage demonstration project for over 15 years. The project involved investigating the properties of the concrete shield. INL performed a survey of the cask in the summers of 2003 and 2004. The INL team met with the CRIEPI representatives in December of 2004 to discuss the next steps. As a result of that meeting, CRIEPI requested that in the summer 2005 INL perform additional surveys on the VSC 17 cask with participation of CRIEPI scientists. This document summarizes the evaluation methods used on the VSC 17 to evaluate the cask for compressive strength, concrete cracking, concrete thickness, and temperature distribution.
Nondestructive Evaluation of LWR Spent Fuel Shipping Casks
Author: Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
An analysis of nondestructve testing (NDT) methods currently being used to evaluate the integrity of Light Water Reactor (LWR) spent fuel shipping casks is presented. An assessment of anticipated NDT needs related to breeder reactor cask requirements is included. Specific R and D approaches to probable NDT problem areas such as the evaluation of austenitic stainless steel weldments are outlined. A comprehensive bibliography of current NDT methods for cask evaluation in the USA, Great Britain, Japan and West Germany was compiled for this study.
Radioactive Waste Management
Author: Publisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 622
Book Description
A Preliminary Evaluation of the Ability of From-reactor Casks to Geometrically Accommodate Commercial LWR Spent Nuclear Fuel
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 8
Book Description
The Department of Energy has sponsored a number of cask design efforts to define several transportation casks to accommodate the various assemblies expected to be accepted by the Federal Waste Management System. At this time, three preliminary cask designs have been selected for the final design--the GA-4 and GA-9 truck casks and the BR-100 rail cask. In total, this assessment indicates that the current Initiative I cask designs can be expected to dimensionally accommodate 100% of the PWR fuel assemblies (other than the extra-long South Texas Fuel) with control elements removed, and>90% of the assemblies having the control elements as an integral part of the fuel assembly. For BWR assemblies,>99% of the assemblies can be accommodated with fuel channels removed. This paper summarizes preliminary results of one part of that evaluation related to the ability of the From-Reactor Initiative I casks to accommodate the physical and radiological characteristics of the Spent Nuclear Fuel projected to be accepted into the Federal Waste Management System. 3 refs., 5 tabs.
Final Version Dry Cask Storage Study
Author: United States. Department of EnergyPublisher:
ISBN:
Category : Radioactive waste disposal
Languages : en
Pages : 380
Book Description