Large Calorimeter Fire Testing
Abstract not provided.
Publications
Overview of Computer Codes Used for Certification
Abstract not provided.
NRC SPENT FUEL TRANSPORTATION RISK ASSESSMENT METHODOLOGY
Abstract not provided.
TEMPERATURE RESPONSE OF A RAIL-CASK-SIZE PIPE CALORIMETER IN LARGE-SCALE POOL FIRES
Abstract not provided.
RECENT ASSESSMENTS IN THE U.S. OF SPENT FUEL PACKAGES EXPOSED TO SEVERE THERMAL ENVIRONMENTS DIFFERENT FROM REGULATORY STANDARDS
Abstract not provided.
COMPARISON OF UF6 PACKAGES UNDER CERTIFICATION TEST AND ACCIDENT CONDITIONS
Abstract not provided.
Package Development and SAR Preparation
Abstract not provided.
Transportation Overview
Abstract not provided.
Meeting Regulatory Requirements
Abstract not provided.
SNL SAR Review: Thermal
Abstract not provided.
Overview of Transportation & Facility Safety and Security Work Performed for the NRC
Abstract not provided.
Temperature conditioning of large packages for impact testing
Abstract not provided.
Thermal Analysis of a Spent Fuel Cask as if it Were Involved in a Realistic Transportation Accident that Resulted in a Severe Fire
Abstract not provided.
Thermal performance of a spent nuclear fuel transportation package exposed to different tunnel fires
Abstract not provided.
Response of a rail cask to long exposures of small and offset pool fires
Abstract not provided.
Thermal analysis of spent nuclear fuel packages exposed to selected severe historic accidents involving fires
Abstract not provided.
Users manual for CAFE-3D : a computational fluid dynamics fire code
The Container Analysis Fire Environment (CAFE) computer code has been developed to model all relevant fire physics for predicting the thermal response of massive objects engulfed in large fires. It provides realistic fire thermal boundary conditions for use in design of radioactive material packages and in risk-based transportation studies. The CAFE code can be coupled to commercial finite-element codes such as MSC PATRAN/THERMAL and ANSYS. This coupled system of codes can be used to determine the internal thermal response of finite element models of packages to a range of fire environments. This document is a user manual describing how to use the three-dimensional version of CAFE, as well as a description of CAFE input and output parameters. Since this is a user manual, only a brief theoretical description of the equations and physical models is included.
Safety of RAM packages - rail transport
Abstract not provided.
The use of cafe-3D for the simulation of tunnel fires
Abstract not provided.
Calibration of the cafe-3D fire code with controlled indoor fire data
Abstract not provided.
Effect of small long-duration fires on a spent nuclear fuel transportation package
Abstract not provided.
Thermal modeling of crushed impact limiters
Abstract not provided.
Comparison of selected highway and railway accidents to the 10CFR71 hypothetical accident sequence and NRC risk assessments
Abstract not provided.
Fire analysis of a spent nuclear fuel dry storage cask using the CAFE-3D fire code
Abstract not provided.
Thermal analyses performed for the NRC Package Performance Study (PPS) test protocols
Abstract not provided.
Results 26–50 of 54