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WHF and RF Thermal Evaluation
WHF and RF Thermal Evaluation
Managing Nuclear Waste - A Better Idea
Managing Nuclear Waste - A Better Idea
All activities which involve the use of radioactive material inevitably result in nuclear waste as a by-product of their operation. Most of the waste produced by such activities as medical diagnosis and therapy, field and laboratory research, and industrial processes is low-level radioactive waste—primarily small amounts of radioactivity in a large volume of matter.
Radiation Effects of Isotopic Uncertainty for Burnup Credit Validation
Radiation Effects of Isotopic Uncertainty for Burnup Credit Validation
The objective of this calculation is to provide the uncertainty term for fission product and minor actinides which contributes to the determination of the critical limit for burnup credit calculations. The scope of this calculation covers PWR and BWR spent nuclear fuel. This activity supports the Criticality Department's validation of burnup credit. The intended use of these results is in future Criticality Department calculations and analyses.
DSNF and Other Waste Form Degradation Abstraction
DSNF and Other Waste Form Degradation Abstraction
Several hundred distinct types of DOE-owned spent nuclear fuel (DSNF) may potentially be disposed in the Yucca Mountain repository. These fuel types represent many more types than can be viably individually examined for their effect on the Total System Performance Assessment for the License Application (TSPA-LA). Additionally, for most of these fuel types, there is no known direct experimental test data for the degradation and dissolution of the waste form in repository groundwaters.
Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel – Executive Summary
Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel – Executive Summary
The U.S. Nuclear Waste Technical Review Board (Board) is tasked by the amendments to the Nuclear Waste Policy Act of 1982 to independently evaluate U. S. Department of Energy (DOE) technical activities for managing and disposing of used nuclear fuel and high-level radioactive waste. This report was prepared to inform DOE and Congress about the current state of the technical basis for extended dry storage1 of used fuel and its transportation following storage.
1999 Design Basis Waste Input Report for Commercial Spent Nuclear Fuel
1999 Design Basis Waste Input Report for Commercial Spent Nuclear Fuel
The purpose of this document is to provide waste quantity and sequencing information that serves as the design basis for commercial spent nuclear fuel (CSNF) arriving at the repository, and the information on the transportation systems that will be used to deliver this fuel. It is intended as input for waste package and repository design analyses needed to ensure that facilities are flexible enough to be capable of receiving, unloading, handling, and emplacing the amounts and types of CSNF expected for receipt under realistic bounding conditions.
Long-term Safety for KBS-3 Repositories at Forsmark and Laxemar—a First Evaluation: Main Report of the SR-Can project
Long-term Safety for KBS-3 Repositories at Forsmark and Laxemar—a First Evaluation: Main Report of the SR-Can project
This document is the main report from the safety assessment project SR-Can. The SR-Can project is a preparatory stage for the SR-Site assessment, the report that will be used in support of SKB’s application for a final repository. The purposes of the safety assessment SR-Can are the following:
1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant.
Attachment 2 - Annual Cost Profile (in Millions of 2007$), reply to Letter to Mr. Tim Frazier
Attachment 2 - Annual Cost Profile (in Millions of 2007$), reply to Letter to Mr. Tim Frazier
The table is based on historical costs through 2006, which are shaded, and projected costs in the 2008 TSLCC. To convert to 2010$, multiply by 1.0586. The 2008 TSLCC assumes a single repository system capable of accepting and disposing of SNF and HLW equivalent to 122,100 Metric Tons of Heavy Metal (MTHM). This estimate includes all defense wastes currently destined for disposal at Yucca Mountain and projected discharges of SNF from commercial utilities, including the 47 nuclear power reactors that had received license extensions from the NRC as of January 2007.
Engineered Barrier System: Physical and Chemical Environment
Engineered Barrier System: Physical and Chemical Environment
The purpose of this model report is to describe the evolution of the physical and chemical environmental conditions within the waste emplacement drifts of the repository, including the drip shield and waste package surfaces. This report documents the development of a new process-level model, the near-field chemistry (NFC) model, and develops two abstraction models.
Configuration Generator Model
Configuration Generator Model
The Disposal Criticality Analysis Methodology Topical Report prescribes an approach to the methodology for performing postclosure criticality analyses within the monitored geologic repository at Yucca Mountain, Nevada. An essential component of the methodology is the Configuration Generator Model for In-Package Criticality that provides a tool to evaluate the probabilities of degraded configurations achieving a critical state.