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Lessons Learned from the West Valley Spent Nuclear Fuel Shipment within the United States

This paper describes the lessons learned from the U.S. Department of Energy (DOE) transportation of
125 DOE-owned commercial spent nuclear fuel (SNF) assemblies by railroad from the West Valley Demonstration
Project to the Idaho National Engineering and Environmental Laboratory (INEEL). On July 17, 2003, DOE made
the largest single shipment of commercial SNF in the history of the United States. This was a highly visible and
political shipment that used two specially designed Type B transportation and storage casks. This paper describes


Why DOE's Messages on Transportation Don't Resonate with the Public (and What DOE Can Do to Fix the Problem)

This paper describes the U.S. Department of Energy’s (DOE) challenge in addressing public perceptions about the planned transport of spent nuclear fuel and high-level nuclear waste to a national repository. The authors focus on ways to improve one small but important component of a well-designed effort to manage social risk – namely, public outreach. After reviewing fundamental principles of risk perception, the authors examine DOE’s own public information materials from various radioactive waste shipping campaigns to determine the extent to which DOE uses such messages.

Application of Sensitivity/Uncertainty Methods to Burnup Credit Criticality Validation

The responsible use of calculational methods in nuclear criticality safety includes a determination of bias and bias uncertainty that may exist between the calculated results and reality. Such biases exist due to approximations used to model the real world, uncertainties in nuclear data, and approximations associated with the calculational method (e.g., Monte Carlo method). The bias and bias uncertainty are typically determined by using the modeling approximations, nuclear data, and calculational method to model well-known, usually critical, systems.

Research Supporting Implementation of Burnup Credit in the Criticality Safety Assessment of Transport and Storage Casks

The Nuclear Regulatory Commission (NRC) Office of Regulatory Research (RES) has initiated a program to support effective implementation of burnup credit in the criticality safety assessment of transport and dry storage casks. The goal is to develop technical bases that can be used to provide criteria and guidance for use in licensing activities. The program is being conducted in a phased approach, with the initial focus on unresolved issues related to the use of actinide-only bumupcredit in transport and dry storage casks designed for spent fuel from pressurized-water reaciors (PWRs).