Download or read book Cask Drop Testing and Analysis written by and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Packages designed to carry spent fuel within the United States must be approved and certified by the Nuclear Regulatory Commission (NRC). This is done by submitting an application to the NRC that describes the package design and provides a detailed technical evaluation of its performance under a variety of normal and accident conditions. These technical evaluations are often based on a combination of theoretical analysis and experimental testing that can be particularly important if it is necessary to corroborate specific analytical assumptions or confirm the methodology used. Tests can be applied to full-scale prototypes or scale model packages, either of which can frequently provide the necessary evidence to substantiate the conclusions. This report discusses two types of packages that were tested at the Oak Ridge National Laboratory -- a scale model spent fuel cask and a full-scale canister designed to be carried inside a spent fuel cask. They were designed by two private companies. Both companies applied to the NRC for a Certificate of Compliance for their casks. In both cases, the combination of testing and analysis, and the way it was applied, formed a critical part of their application. 7 refs., 2 figs., 1 tab.

Download or read book Static and Impact Tests on 15 ton Cask for Shipping Irradiated Fuel written by W. I. Thisell and published by . This book was released on 1963 with total page 164 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Numerical Simulation of the One Meter Drop Test on a Bar for the Castor Cask written by Nikola Jakšić and published by . This book was released on 2007 with total page 108 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Casks computer Analysis of Storage Casks written by and published by . This book was released on 1995 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: CASKS is a microcomputer based computer system developed by LLNL to assist the Nuclear Regulatory Commission in performing confirmatory analyses for licensing review of radioactive-material storage cask designs. The analysis programs of the CASKS computer system consist of four modules: the impact analysis module, the thermal analysis module, the thermally-induced stress analysis module, and the pressure-induced stress analysis module. CASKS uses a series of menus to coordinate input programs, cask analysis programs, output programs, data archive programs and databases, so the user is able to run the system in an interactive environment. This paper outlines the theoretical background on the impact analysis module and the yielding surface formulation. The close agreement between the CASKS analytical predictions and the results obtained form the two storage casks drop tests performed by SNL and by BNFL at Winfrith serves as the validation of the CASKS impact analysis module.

Download or read book Destructive Drop Tests of a Model Fuel Shipping Cask written by G. L. Saywell and published by . This book was released on 1964 with total page 62 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Summary and Evaluation of Steel Billet Testing written by and published by . This book was released on 1998 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Tests were performed at Sandia National Laboratories (SNL) and Lawrence Livermore National Laboratory (LLNL) to assess loading conditions on a spent fuel storage cask for end drops, side drops and tipover events. The tests were performed with a 1/3-scale model billet and a 1/3-scale model concrete pad, and included a variety of substrate materials. A NUREG/CR report was prepared for the Nuclear Regulatory Commission (NRC) and provides a summary and an evaluation of all the billet testing conducted. This paper provides a description of the testing and analysis method, and a summary of the results. A generic or representative cask was modeled with the benchmarked finite element analysis approach and evaluated for ISFSI end and side drops and tipover events. The analytical method can be applied to similar casks to estimate deceleration loads on storage casks resulting from low-velocity drop or tipover impacts onto concrete storage pads.

Download or read book Radioactive Waste Management written by and published by . This book was released on 1981 with total page 726 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book IMPACT ANALYSIS OF SPENT FUEL DRY CASKS UNDER ACCIDENTAL DROP SCENARIOS written by J. XU and published by . This book was released on 2003 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt: A series of analyses were performed to assess the structural response of spent nuclear fuel dry casks subjected to various handling and on-site transfer events. The results of these analyses are being used by the Nuclear Regulatory Commission (NRC) to perform a probabilistic risk assessment (PRA). Although the PRA study is being performed for a specific nuclear plant, the PRA study is also intended to provide a framework for a general methodology that could also be applied to other dry cask systems at other nuclear plants. The dry cask system consists of a transfer cask, used for handling and moving the multi-purpose canister (MPC) that contains the fuel, and a storage cask, used to store the MPC and fuel on a concrete pad at the site. This paper describes the analyses of the casks for two loading events. The first loading consists of dropping the transfer cask while it is lowered by a crane to a concrete floor at ground elevation. The second loading consists of dropping the storage cask while it is being transferred to the concrete storage pad outdoors. Three dimensional finite element models of the transfer cask and storage cask, containing the MPC and fuel, were utilized to perform the drop analyses. These models were combined with finite element models of the target structures being impacted. The transfer cask drop analyses considered various drop heights for the cask impacting the reinforced concrete floor at ground level. The finite element model of the target included a section of the concrete floor and concrete wall supporting the floor. The storage cask drop analyses evaluated a 30.5 cm (12 in.) drop of the cask impacting three different surfaces: reinforced concrete, asphalt, and gravel.

Download or read book Energy Research Abstracts written by and published by . This book was released on 1994-10 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Analysis of a Hypothetical Dropped Spent Nuclear Fuel Shipping Cask Impacting a Floor Mounted Crush Pad written by and published by . This book was released on 1998 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: A crush pad has been designed and analyzed to absorb the kinetic energy of a hypothetically dropped spent nuclear fuel shipping cask into a 44-ft. deep cask unloading pool at the Idaho Chemical Processing Plant. The 110-ton Large Cell Cask was assumed to be accidentally dropped onto the parapet of the unloading pool, causing the cask to tumble through the pool water and impact the floor mounted crush pad with the cask's top corner. The crush pad contains rigid polyurethane foam, which was modeled in a separate computer analysis to simulate the manufacturer's testing of the foam and to determine the foam's stress and strain characteristics. This computer analysis verified that the foam was accurately represented in the analysis to follow. A detailed non-linear, dynamic finite element analysis was then performed on the crush pad and adjacent pool structure to assure that a drop of this massive cask does not result in unacceptable damage to the storage facility. Additionally, verification was made that the crush pad adequately protects the cask from severe impact loading. At impact, the cask has significant vertical, horizontal and rotational velocities. The crush pad absorbs much of the energy of the cask through plastic deformation during primary and secondary impacts. After the primary impact with the crush pad, the cask still has sufficient energy to rebound and rotate until it impacts the pool wall. An assessment is made of the damage to the crush pad and pool wall and of the impact loading on the cask.

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 640 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book ERDA Energy Research Abstracts written by United States. Energy Research and Development Administration and published by . This book was released on 1976-05 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Cask Crush Pad Analysis Using Detailed and Simplified Analysis Methods written by and published by . This book was released on 1997 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: A crush pad has been designed and analyzed to absorb the kinetic energy of a hypothetically dropped spent nuclear fuel shipping cask into a 44-ft. deep cask unloading pool at the Fluorinel and Storage Facility (FAST). This facility, located at the Idaho Chemical Processing Plant (ICPP) at the Idaho national Engineering and Environmental Laboratory (INEEL), is a US Department of Energy site. The basis for this study is an analysis by Uldrich and Hawkes. The purpose of this analysis was to evaluate various hypothetical cask drop orientations to ensure that the crush pad design was adequate and the cask deceleration at impact was less than 100 g. It is demonstrated herein that a large spent fuel shipping cask, when dropped onto a foam crush pad, can be analyzed by either hand methods or by sophisticated dynamic finite element analysis using computer codes such as ABAQUS. Results from the two methods are compared to evaluate accuracy of the simplified hand analysis approach.

Download or read book Rules and Regulations written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1987 with total page 900 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Federal Register written by and published by . This book was released on 1993-04 with total page 1158 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Basic Of Transport And Storage Of Radioactive Materials written by Toshiari Saegusa and published by World Scientific. This book was released on 2018-04-09 with total page 399 pages. Available in PDF, EPUB and Kindle. Book excerpt: Safe and secure transport and storage of radioactive materials are essential for sustainable nuclear fuel cycle. The basic technologies are matured, but they have been progressively developed to make transport and storage safer and more secure. Safe and secure culture that encourages a questioning and learning attitude and that discourages complacency should be fostered and maintained. This book provides current basis of safe and secure transport and storage so that those technologies can be readily traced, improved, or modified, if necessary, for and by the future generations.This book overviews current available information in the literature. It also covers advanced technology on similar subjects in the literature. On top of that, new and valuable subjects are introduced for readers to grasp the wide spectrum of the safe and secure transport and storage technology. The contents are arranged and divided into three sections, I: Safety of Transport, II: Safety of Storage, III: Security of Transport and Storage.

Download or read book Final Version Dry Cask Storage Study written by United States. Department of Energy and published by . This book was released on 1989 with total page 380 pages. Available in PDF, EPUB and Kindle. Book excerpt: