slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

CSNF Loading Curve Sensitivity Analysis

The purpose of this scientific analysis report, CSNF Loading Curve Sensitivity Analysis, is to establish the required minimum burnup as a function of initial enrichment for both pressurized water reactor (PWR) and boiling water reactor (BWR) commercial spent nuclear fuel (CSNF) that would allow permanent disposal of these waste forms in the geologic repository at Yucca Mountain. The relationship between the required minimum burnup and fuel assembly initial enrichment forms a loading curve.

DOE SNF Phase I and II Summary Report

There are more than 250 forms of U.S. Department of Energy (DOE)­owned spent nuclear fuel (SNF). Due to the variety of the spent nuclear fuel, the National Spent Nuclear Fuel Program (NSNFP) has designated nine representative fuel groups for disposal criticality analyses based on fuel matrix, primary fissile isotope, and enrichment. For each fuel group, a fuel type that represents the characteristics of all fuels in that group has been selected for detailed analysis.

Initial Radionuclide Inventories

The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only.

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1, Burnup Credit in the Criticality Safety Analyses of PWR Spent Fuel in Transport and Storage Casks

Spent Fuel Project Office, Interim Staff Guidance - 8, Revision 1

OECD/NEA Burnup Credit Criticality Benchmarks Phase IIIB: Burnup Calculations of BWR Fuel Assemblies for Storage and Transport

The report describes the final results of the Phase IIIB Benchmark conducted by the Expert Group on Burnup Credit Criticality Safety under the auspices of the Nuclear Energy Agency (NEA) of the Organization for Economic Cooperation and Development (OECD). The Benchmark was intended to compare the predictability of current computer code and data library combinations for the atomic number densities of an irradiated BWR fuel assembly model. The fuel assembly was irradiated under specific power of 25.6 MW/tHM

Drift-Scale THC Seepage Model

The purpose of this report is to document the thermal-hydrologic-chemical (THC) seepage model and model simulations. The simulations predict the composition of fracture water that could potentially seep into repository emplacement drifts and the composition of the associated gas phase. The THC seepage model is not used to feed the total system performance assessment (TSPA) for the license application (LA).

Internationalization of the Nuclear Fuel Cycle

Following the proposals for nuclear fuel assurance of International Atomic Energy Agency (IAEA) Director General Mohamed El Baradei, former Russian President Vladimir V. Putin, and U.S. President George W. Bush, joint committees of the Russian Academy of Sciences (RAS) and the U.S. National Academies (NAS) were formed to address these and other fuel assurance concepts and their links to nonproliferation goals. The joint committees also addressed many technology issues relating to the fuel assurance concepts. This report provides

User Manual for the Total System Model Version 6.0 Preprocessor

The Total System Model Preprocessor (TSMPP) is a part of the Total System Model (TSM), which is a PC-based simulator that is a decision aid to achieve overall Office of Civilian Radioactive Waste Management (OCRWM) disposal objectives. The TSMPP combines information about existing conditions, such as waste inventory estimates and site capabilities, with projections of future conditions, such as projected waste discharges and expected cask capabilities, to provide a waste shipment schedule that is input to the TSM. The TSM then uses

Summary Report of Commercial Reactor Criticality Data for Davis-Besse Unit 1

The "Summary Report of Commercial Reactor Criticality Data for Davis-Besse Unit 1" contains the detailed information necessary to perform commercial reactor criticality (CRC) analyses for the Davis-Besse Unit 1 reactor.

Preclosure Criticality Analysis Process Report

The preclosure criticality analysis process described in this technical report provides a systematic approach for determining the need for criticality controls and for evaluating their effectiveness during the preclosure period of the Monitored Geologic Repository at Yucca Mountain, Nevada.

Reactor and Fuel Cycle Technology Subcommittee Report to the Full Commission DRAFT

The Reactor and Fuel Cycle Technology Subcommittee was formed to respond to the charge—set forth in the charter of the Blue Ribbon Commission—to evaluate existing fuel cycle technologies and R&D programs in terms of multiple criteria.

EQ6 Calculation for Chemical Degradation of Pu-Ceramic Waste Packages: Effects of Updated Materials Composition and Rates

The Monitored Geologic Repository (MGR) Waste Package Operations (WPO) of the Civilian Radioactive Waste Management System Management and Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of Pu-ceramic waste forms. The Pu- ceramic (Refs. 1 and 2) is designed to immobilize excess plutonium from weapons production, and has been considered for disposal at the potential Yucca Mountain site.

Total System Model Version 6.0 Cost Estimating Routines Design and Bases

This manual discusses the cost estimating routines used in Version (V) 6.0 of the Total System Model (TSM) as described in the TSM User Manual (BSC 2007a). The TSM estimates costs during the simulation of the Civilian Radioactive Waste Management System (CRWMS) mission. The TSM is not intended to provide a full Total System Life Cycle Cost (TSLCC) evaluation tool but focuses on the CRWMS Waste Acceptance, Storage, and Transportation (WAST) elements reported for the TSLCC in Reference BSC 2003a. This manual also

slides - Operating Experience, Session I, Cask Cranes

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

slides - Transportation Infrastructure

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

Technical Evaluation Report on the Content of the U.S. Department of Energy's Yucca Mountain Repository License Application

This “Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain License Application; Postclosure Volume: Repository Safety After Permanent Closure” (TER Postclosure Volume) presents information on the NRC staff’s review of DOE’s Safety Analysis Report (SAR), provided on June 3, 2008, as updated by DOE on February 19, 2009. The NRC staff also reviewed information DOE provided in response to NRC staff’s requests for additional information and other information that DOE provided related to the SAR.

Nuclear Waste Discussion Draft - FLO13341 - 113th Congress - 1st Session

To establish a new organization to manage nuclear waste, provide a consensual process for siting nuclear waste facilities, ensure adequate funding for managing nuclear waste, and for other purposes.

CRC Depletion Calculations for LaSalle Unit I

The purpose of this calculation is to document the LaSalle Unit 1 boiling water reactor (BWR) fuel depletion calculations performed as part of the commercial reactor critical (CRC) evaluation program. The CRC evaluations constitute benchmark calculations that support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository. This calculation incorporates control blade effects and minor variations in the SAS2H assembly modeling.

Transuranic Burning Issues Related to a Second Geologic Repository

This report defines issues that need to be addressed by a development program recently initiated to establish the viability of a transuranic program recently initiated to establish the viability of a transuranic burning concept application that would achieve a substantial delay to the need date for a second geologic repository. The visualized transuranic burning concept application is one in which spent fuel created after a date in the 2010 timeframe or later would be processed and the separated plutonium used to start up liquid metal reactors.

Criticality Model

The Disposal Criticality Analysis Methodology Topical Report (YMP 2003) presents the methodology for evaluating potential criticality situations in the monitored geologic repository. As stated in the referenced Topical Report, the detailed methodology for performing the disposal criticality analyses will be documented in model reports. Many of the models developed in support of the Topical Report differ from the definition of models as given in the Office of Civilian Radioactive Waste Management procedure AP-SIII.10Q, Models, in that they are procedural, rather than mathematical.

NRC Waste Confidence Positions

In response to the remand of the U.S. Court of Appeals for the District of Columbia Circuit (Minnesota v. NRC, 602 F.2d 412 (1979)), and as a continuation of previous proceedings conducted in this area by NRC (44 Fed. Reg. 61,372), the Commission initiated a generic rulemaking proceeding on October 25, 1979.

Second Waste Package Probabilistic Criticality Analysis: Generation and Evaluation of Internal Criticality Configurations

This analysis is prepared by the Mined Geologic Disposal System (MODS) Waste Package Development (WPD) department to provide an evaluation of the criticality potential within a waste package having some or all of its contents degraded by corrosion and removal of neutron absorbers. This analysis is also intended to provide an estimate of the consequences of any internal criticality, particularly in terms of any increase in radionuclide inventory. These consequence estimates will be used as part of the WPD input to the Total System Performance Assessment.

slides - Cumulative Impact of Industry and NRC Actions

Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013

Laboratory Critical Experiment Reactivity Calculations

The purpose of this calculation is to perform the same reactivity calculations as performed in Reference 7.1 and Reference 7.2 for a set of Laboratory Critical Experiments (LCE) except to change some of the cross section libraries as specified here, and to perform sixteen additional calculations for U233 LCEs.