slides - Operating Experience

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

Design Evolution Study: Thermal Operating Methodology

This study provides results supporting the conclusion that the repository can be operated over a varying range of thermal modes and therefore temperatures. In particular, this work focused on limiting the peak, postclosure waste package surface temperature to less than 85 degrees Celsius, a possible limit due to corrosion considerations. These operating modes were compared by varying the waste package in drift spacing (0.1-2.83 meters), drift pitch (drift spacing centerline to centerline of 40-120 meters), ventilation duration (75-300 years), and ventilation efficiency (50-80%).

Legal Analysis of Commission Recommendations for Near-Term Actions

At the request of the staff to the Blue Ribbon Commission on America’s Nuclear Future (“BRC”), we have reviewed whether certain recommendations in the BRC’s July 29, 2011 Draft Report respecting near-term actions by the Department of Energy (“DOE”) or other officers or agencies in the Executive Branch can be implemented under existing law. These recommendations relate to: (1) Initial steps to site, license and construct consolidated interim storage facilities for spent nuclear fuel (“spent fuel”);

Fast Flux Test Facility (FFTF) Reactor Fuel Degraded Criticality Calculation: Degraded SNF Canister

The objective of this calculation is to characterize the criticality aspect of a Department of Energy Spent Nuclear Fuel (DOE SNF) canister containing 5 Fast Flux Test Facility (FFTF) assemblies in a Five-Pack defense High-Level Waste (HLW) waste package. The purpose of this calculation is to investigate the criticality issues for the waste package (WP) containing HLW and DOE SNF canisters in various stages of degradation.

SOCIAL DISTRUST: IMPLICATIONS AND RECOMMENDATION FOR SPENT NUCLEAR FUEL AND HIGH LEVEL RADIOACTIVE WASTE MANAGEMENT

The management of spent nuclear fuel (SNF) and defense high level waste (HLW) is a complex sociotechnical systems challenge. Coordinated, reliable, and safe performance will be required over very long periods of time within evolving social and technical contexts. To accomplish these goals, a waste management system will involve a host of facilities for interim storage and longterm disposal, a transportation infrastructure, and research and development centers. The complexity of SNF and HLW

Yankee Atomic Electric Company vs The United States, November 14, 2013

Spent Nuclear Fuel Litigation - Court of Federal Claims decision in Maine Yankee II, Conn Yankee II and Yankee Atomic II

slides - Deep Borehole Disposal of Spent Fuel

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

Geological Disposal of Radioactive Waste

The objective of this safety requirements publication is to set down the protection objectives and criteria for geological disposal and to establish the requirements that must be met to ensure the safety of this disposal option, consistent with the established principles of safety for radioactive waste management.

Commercial Spent Nuclear Fuel Waste Package Misload Analysis

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that

Nuclear Criticality Calculations for Canister-Based Facilities - Commercial SNF

The purpose of this calculation is to perform waste-form specific nuclear criticality safety calculations to aid in establishing criticality safety design criteria, and to identify design and process parameters that are potentially important to the criticality safety of the transportation, aging and disposal (TAD) canister-based systems.

Nuclear Waste: Is There A Need For Federal Interim Storage?

About 20,000 metric tons of spent, or used, nuclear fuel have accumulated since the beginning of commercial nuclear power prbduction in the United States. At the end of the currently licensed period of all existing nuclear power plants and those under construction, the amount of spent nuclear fuel is expected to total 87,000 metric tons. Thus far, practically all of the spent nuclear fuel is stored in water-filled pools at reactor sites. However, space does not exist in the pools to store all the spent fuel expected

Qualification of Thermodynamic Data for Geochemical Modeling of Mineral–Water Interactions in Dilute Systems

This report is developed from Technical Work Plan for: Thermodynamic Databases for Chemical Modeling (BSC 2006 [DIRS 177885]). The purpose of this analysis report is to update the thermochemical database data0.ymp.R4 (Output DTN: SN0410T0510404.002). Various data have been added, corrected, or corroborated, partly in response to four Condition Reports (CRs): CR 6489, CR 6731, CR 7542, and CR 7756. The most notable changes are a general revision of phosphate data to achieve consistency with the recommendations from the Committee on Data for Science and Technology (CODATA) (Cox. et al.

SAS2H Analysis of Radiochemical Assay Samples from Turkey Point PWR Reactor

The purpose of this design analysis is to determine the accuracy of the SAS2H module of SCALE 4.3 in predicting isotopic concentrations of spent fuel assemblies. The objective is to develop a methodology for modeling assemblies similar to those evaluated within this analysis and to establish the consistency of SAS2H predictions. The results of this analysis may then be applied·to future depletion calculations using SAS2H in which no measurements are available. ·

Used Fuel Disposition U.S. Radioactive Waste Inventory and Characteristics Related to Potential Future Nuclear Energy Systems

In February, 2011 the Blue Ribbon Commission (BRC) on America’s Nuclear Future requested the Department of Energy (DOE) to provide a white paper summarizing the quantities and characteristics of potential waste generated by various nuclear fuel cycles. The BRC request expressed interest in two classes of radioactive wastes:  Existing waste that are or might be destined for a civilian deep geologic repository or equivalent.  Potential future waste, generated by alternative nuclear fuel cycles (e.g. wastes from reprocessing, mixed-oxide

Actinide-Only Burnup Credit License Application: the CASTOR X/32 S Cask Modeling Details

Occupational Risk Consequences of the Department of Energy's Approach to Repository Design, Performance Assessment, and Operation in the Yucca Mountain License Application

EPRI has discovered several aspects of the U.S Department of Energy (DOE) proposed design and operation of the Yucca Mountain repository that—if implemented as described in the license application (LA)—could result in unnecessary occupational health and safety risk to workers involved with repository-related activities. This report identifies key DOE conservatisms and focuses on the occupational risk consequences of the DOE's approach to the repository design, performance assessment, and operation.

Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites

This report discusses the status of the commercial spent nuclear fuel (SNF) inventory in the United States, at both decommissioned and operating commercial nuclear power reactor sites; summarizes the contractual arrangement the government and utilities have under the Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste (10 CFR Part 961) (Standard Contract), related litigation, and the financial liabilities resulting from the Department’s delay in performance under these contracts; provides a history of interim storage policy as it relates to commercial SN

From Integral Experiments to Nuclear Data Improvement

Target accuracy on LWR neutronics parameters is 2 to 5 times lower than the a priori uncertainty (1σ) due to nuclear data. This paper summarizes the experimental facilities and the integral measurements that are required for code qualification. The rigorous use of integral information through trend analysis method is described. Trends on JEF2 data from Keff measurements and P.I.Es are presented. These trends were accounted for in the new JEFF3 evaluations. The role of fundamental experiments, such as worth measurement of separated isotopes, is emphasized.

In-Drift Precipitates/Salts Model

This report documents the development and validation of the in-drift precipitates/salts (IDPS) process model. The IDPS process model is a geochemical model designed to predict the postclosure effects of evaporation and deliquescence on the chemical composition of water within the Engineered Barrier System (EBS) in support of the total system performance assessment (TSPA). Application of the model in support of TSPA is documented in Engineered Barrier System: Physical and Chemical Environment (BSC 2005 [DIRS 175083]).

Evaluation of Burnup Credit for Accommodating PWR Spent Nuclear Fuel in High-capacity Cask Designs

This paper presents an evaluation of the amount of burnup credit needed for high-density casks to transport the current U.S. inventory of commercial spent nuclear fuel (SNF) assemblies. A prototypic 32-assembly cask and the current regulatory guidance were used as bases for this evaluation. By comparing actual pressurized-water-reactor (PWR) discharge data (i.e., fuel burnup and initial enrichment specifications for fuel assemblies discharged from U.S. PWRs) with actinide-only-based

Monitored Retrievable Storage Project Plan

The purpose of this document is to describe the Monitored Retrievable Storage (MRS) Project and to establish approved cost and schedule baselines against which overall progress and management effectiveness shall be measured. For the sake of brevity, this Project Plan will be referred to as the Plan throughout this document.

Alternative Means of Financing and Managing the Civilian Radioactive Waste Management Program

This report is in response to the directive of the House Appropriations Subcommittee for Energy and Water Development that the Department of Energy (DOE) update a 1984 report of alternative means of financing and managing (AMFM) the Office of Civilian Radioactive Waste Management (OCRWM) in the DOE. The President’s FY 2002 budget also stated: “DOE will submit to Congress an updated report regarding alternative approaches to finance and manage the program by June 30, 2001[.] DOE will identify in this report models of

Criticality Evaluation of Degraded Internal Configurations for a 44 BWR Waste Package

The purpose of this calculation is to perform an example criticality evaluation for degraded internal configurations of a boiling water reactor (BWR) waste package (WP) containing 44 spent nuclear fuel (SNF) assemblies.

Advances in Applications of Burnup Credit to Enhance Spent Fuel Transportation, Storage, Reprocessing and Disposition-Proceedings of a Technical Meeting held in London, 29 August-2 September 2006

This publication records the proceedings of a technical meeting organized by the IAEA and held in London 29 August–2 September 2005 with sixty participants from 18 countries. As indicated in the title, the objective of this meeting was to provide a forum for exchange of technical information on spent fuel burnup credit applications and thereby compile state-ofthe- art information on technical advances related to spent fuel transportation, storage, reprocessing and disposition.

slides - Canister Confinement Integrity, Integrated Plan for Addressing Potential Chloride-Induced Stress Corrosion Cracking of Austenitic Stainless Steel Dry Cask Storage System Canisters

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