Download or read book Evaluation of the Use of Homogenized Fuel Assemblies in the Thermal Analysis of Spent Fuel Storage Casks written by and published by . This book was released on 1999 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Thermal analysis of spent fuel storage casks has generally been based on the assumption that heat released by the fuel assemblies is transported to the cask cavity only by conduction through the walls of the basket. This conservative assumption was adopted to compensate for uncertainties in modeling heat transfer in the cavity of a spent fuel cask. During recent years, some applications have submitted safety analysis reports for spent fuel storage casks that challenge this assumption. They offer two methods which include the fuel assemblies, as well as the walls of the basket, as part of the path for heat transfer to the cask cavity. A third method, the consideration of a fuel assembly as a homogeneous log, is explored in a study described in this report.
Download or read book Evaluation of Effect of Fuel Assembly Loading Patterns on Thermal and Shielding Performance of a Spent Fuel Storage written by and published by . This book was released on 2001 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: The licensing of spent fuel storage casks is generally based on conservative analyses that assume a storage system being uniformly loaded with design basis fuel. The design basis fuel typically assumes a maximum assembly enrichment, maximum burn up, and minimum cooling time. These conditions set the maximum decay heat loads and radioactive source terms for the design. Recognizing that reactor spent fuel pools hold spent fuel with an array of initial enrichments, burners, and cooling times, this study was performed to evaluate the effect of load pattern on peak cladding temperature and cask surface dose rate. Based on the analysis, the authors concluded that load patterns could be used to reduce peak cladding temperatures in a cask without adversely impacting the surface dose rates.
Download or read book Thermal and Reliability Criteria for Nuclear Fuel Safety written by Maksym Maksymov and published by CRC Press. This book was released on 2022-09-01 with total page 287 pages. Available in PDF, EPUB and Kindle. Book excerpt: The book covers basic approaches to the nuclear fuel state of energy reactors in the last stages of the nuclear fuel cycle, these have been developed by the authors based on Ukrainian Nuclear Power Plant (NPP) operational experience. The book starts by looking at the physical safety basis of water-water energetic reactor (WWER) nuclear fuel. It goes on to discuss modern approaches to the heat exchange modelling in nuclear power plant equipment. Next, the safety criteria when making a decision about dry storage for WWER-1000 fuel assembly are discussed. Then the effect of reactor capacity cyclic changes on energy accumulation of creep formations in fuel cladding is covered in full, along with a chapter on the analysis of WWER-1000 fuel cladding failure. Finally, the book finishes with a description of thermal safety criteria for dry storage of spent nuclear fuel. The book is essential reading for anyone concerned with NPP maintenance and safety.
Download or read book Annual Book of ASTM Standards written by ASTM International and published by . This book was released on 2003 with total page 1484 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Evaluation of Effect of Fuel Assembly Loading Patterns on Thermal and Shielding Performance of a Spent Fuel Storage transportation Cask written by Judith M. Cuta and published by . This book was released on 2001 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Optimization Strategies for Cask Design and Container Loading in Long Term Spent Fuel Storage written by International Atomic Energy Agency and published by . This book was released on 2006 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: Outlines the optimization process for cask design, licensing and utilization, describing three principal groups of optimization activities in terms of relevant technical considerations such as criticality, shielding, structural design, operations, maintenance and retrievability.
Download or read book Federal Register written by and published by . This book was released on 2000-03 with total page 300 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book COBRA SFS Thermal Analysis of a Sealed Storage Cask for the Monitored Retrievable Storage of Spent Fuel written by David R. Rector and published by . This book was released on 1986 with total page 35 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Computational Fluid Dynamics Best Practice Guidelines for Dry Cask Applications written by U.s. Nuclear Regulatory Comion and published by CreateSpace. This book was released on 2014-05-21 with total page 174 pages. Available in PDF, EPUB and Kindle. Book excerpt: ABSTRACT Dry storage cask designs for spent nuclear fuel are submitted to the U.S. Nuclear Regulatory Commission (NRC) for certification under Title 10 of the Code of Federal Regulations (10 CFR) Part 72, “Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High- Level Radioactive Waste, and Reactor-Related Greater Than Class C Waste.” The NRC staff technical review of these designs is performed in accordance with 10 CFR Part 72 and the “Standard Review Plan (SRP) for Spent Fuel Dry Storage Systems at a General License Facility” (NUREG-1536, 2010). To ensure that the cask and fuel material temperatures of the dry cask storage system will remain within the allowable limits or criteria for normal, off-normal, and accident conditions, a thermal review is performed as part of the application's technical review. Recent applications increasingly have used thermal-hydraulic analyses and computational fluid dynamics (CFD) codes (e.g., FLUENT) to demonstrate the adequacy of the thermal design. Therefore, in cooperation with the Division of Spent Fuel Storage and Transportation of the Office of Nuclear Material Safety and Safeguards, the Office of Nuclear Regulatory Research developed this guide to provide practical advice for reviewing CFD methods used in vendor applications and for achieving high-quality CFD simulations of a dry cask. To assist in the analysis, the report includes procedures, analysis methods, and acceptable assumptions.
Download or read book Thermal Analysis of Dry Spent Fuel Transportation and Storage Casks written by Xinhui Chen and published by . This book was released on 1996 with total page 163 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book BWR Spent Fuel Storage Cask Performance Test Volume 2 Pre and Post test Decay Heat Heat Transfer and Shielding Analyses written by and published by . This book was released on with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report describes the decay heat, heat transfer, and shielding analyses conducted in support of performance testing of a Ridhihalgh, Eggers and Associates REA 2033 boiling water reactor (BWR) spent fuel storage cask. The cask testing program was conducted for the US Department of Energy (DOE) Commercial Spent Fuel Management Program by the Pacific Northwest Laboratory (PNL) and by General Electric at the latters' Morris Operation (GE-MO) as reported in Volume I. The analyses effort consisted of performing pretest calculations to (1) select spent fuel for the test; (2) symmetrically load the spent fuel assemblies in the cask to ensure lateral symmetry of decay heat generation rates; (3) optimally locate temperature and dose rate instrumentation in the cask and spent fuel assemblies; and (4) evaluate the ORIGEN2 (decay heat), HYDRA and COBRA-SFS (heat transfer), and QAD and DOT (shielding) computer codes. The emphasis of this second volume is on the comparison of code predictions to experimental test data in support of the code evaluation process. Code evaluations were accomplished by comparing pretest (actually pre-look, since some predictions were not completed until testing was in progress) predictions with experimental cask testing data reported in Volume I. No attempt was made in this study to compare the two heat transfer codes because results of other evaluations have not been completed, and a comparison based on one data set may lead to erroneous conclusions.
Download or read book Rules and Regulations written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1997 with total page 836 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Conceptual Design of Large Spent Fuel Shipping Casks for Older PWR Fuel written by and published by . This book was released on 1983 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this study was to identify realistic designs for large rail casks which have been optimized for the shipment of 2-, 3-, 5-, 7-, and 10-year-old PWR fuel assemblies. To operate and evaluate the various designs, extensive use was made of the SCOPE program which was developed at Oak Ridge National Laboratory as an inexpensive scoping code for Shipping Cask Optimization and Parametric Evaluation using tabulated shielding-thicknesses specified by the user, and a fixed set of optimal packing arrangements, the code will design a cask to carry a single fuel assembly, and then increment the number of assemblies until one of the design limits, such as the overall weight, is exceeded. For each design, the code will calculate the steady-state temperature distribution throughout the cask and perform a complete 1-D space/time transient thermal analysis following a postulated half-hour fire. By using the SCOPE program, a wide range of conceptual designs were evaluated at minimal cost. About 100 cases of potential interest are presented.
Download or read book Safe and Secure Transport and Storage of Radioactive Materials written by Ken Sorenson and published by Woodhead Publishing. This book was released on 2015-07-24 with total page 361 pages. Available in PDF, EPUB and Kindle. Book excerpt: Safe and Secure Transport and Storage of Radioactive Materials reviews best practice and emerging techniques in this area. The transport of radioactive materials is an essential operation in the nuclear industry, without which the generation of nuclear power would not be possible. Radioactive materials also often need to be stored pending use, treatment, or disposal. Given the nature of radioactive materials, it is paramount that transport and storage methods are both safe and secure. A vital guide for managers and general managers in the nuclear power and transport industries, this book covers topics including package design, safety, security, mechanical performance, radiation protection and shielding, thermal performance, uranium ore, fresh fuel, uranium hexafluoride, MOX, plutonium, and more. - Uniquely comprehensive and systematic coverage of the packaging, transport, and storage of radioactive materials - Section devoted to spent nuclear fuels - Expert team of authors and editors
Download or read book Thermal Testing of a Dry Spent Fuel Cask NL1 1 2 Legal Weight Truck Cask written by and published by . This book was released on 1978 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A nuclear spent fuel cask that employs air or an inert gas such as helium as the cooling medium in the fuel cavity is commonly known as a ''dry'' cask. The thermal characteristics of a dry cask differ considerably from a wet cask. A gas is a poorer heat transfer medium than water. As a result, the fuel and cask basket temperatures will be higher for a given fuel heat level. The response characteristics during operating transients will also differ. Detailed thermal tests on a dry cask were performed to verify design parameters and to obtain operational data for shipping and unloading. Results of a number of thermal tests performed on the NL1 1/2 legal weight truck cask are presented. The uniqueness of these tests are that they were performed using a full-scale geometric and thermal mockup of a nuclear fuel assembly. This results in more realistic fuel and basket temperatures being measured than those obtained using a simpler, single heater assembly.
Download or read book Discussion of Available Methods to Support Reviews of Spent Fuel Storage Installation Cask Drop Evaluations written by and published by . This book was released on 2000 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Applicants seeking a Certificate of Compliance for an Independent Spent Fuel Storage Installation (ISFSI) cask must evaluate the consequences of a handling accident resulting in a drop or tip-over of the cask onto a concrete storage pad. As a result, analytical modeling approaches that might be used to evaluate the impact of cylindrical containers onto concrete pads are needed. One such approach, described and benchmarked in NUREG/CR-6608,1 consists of a dynamic finite element analysis using a concrete material model available in DYNA3D2 and in LS-DYNA, 3 together with a method for post-processing the analysis results to calculate the deceleration of a solid steel billet when subjected to a drop or tip-over onto a concrete storage pad. The analysis approach described in NUREG/CR-6608 gives a good correlation of analysis and test results. The material model used for the concrete in the analyses in NUREG/CR-6608 is, however, somewhat troublesome to use, requiring a number of material constants which are difficult to obtain. Because of this a simpler approach, which adequately evaluates the impact of cylindrical containers onto concrete pads, is sought. Since finite element modeling of metals, and in particular carbon and stainless steel, is routinely and accurately accomplished with a number of finite element codes, the current task involves a literature search for and a discussion of available concrete models used in finite element codes. The goal is to find a balance between a concrete material model with a limited number of required material parameters which are readily obtainable, and a more complex model which is capable of accurately representing the complex behavior of the concrete storage pad under impact conditions. The purpose of this effort is to find the simplest possible way to analytically represent the storage cask deceleration during a cask tip-over or a cask drop onto a concrete storage pad. This report is divided into three sections. The Section II provides a summary of the literature search on concrete finite element models. The Section III discusses commercial codes. The Section IV provides recommendations.
Download or read book Thermal Analysis of a Spent Fuel Cask as If it Were Involved in a Realistic Transportation Accident that Resulted in a Severe Fire written by and published by . This book was released on 2006 with total page 8 pages. Available in PDF, EPUB and Kindle. Book excerpt:
