Drift Scale THM Model

This model report documents the drift scale coupled thermal-hydrological-mechanical (THM) processes model development and presents simulations of the THM behavior in fractured rock close to emplacement drifts. The modeling and analyses are used to evaluate the impact of THM processes on permeability and flow in the near-field of the emplacement drifts.

Criticality Evaluation of Degraded Internal Configurations for the PWR AUCF WP Designs

The purpose of this analysis is to provide input on the criticality potential of various degraded configurations to an analysis on the probability of a criticality event in a Pressurized Water Reactor (PWR) Advanced Uncanistered Fuel (AUCF) Waste Package (WP).

Parametric Analysis of PWR Spent Fuel Depletion Parameters for Long-Term Disposal Criticality Safety

Utilization of burnup credit in criticality safety analysis for long-term disposal of spent nuclear fuel allows improved design efficiency and reduced cost due to the large mass of fissile material that will be present in the repository. Burnup-credit calculations are based on depletion calculations that provide a conservative estimate of spent fuel contents (in terms of criticality potential), followed by criticality calculations to assess the value of the effective neutron

slides - Corrosion Monitoring of a Natural Convection Cooled Stored

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

National Transportation Plan

This Plan outlines the Department of Energy’s (DOE) current strategy and planning for developing and implementing the transportation system required to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from where the material is generated or stored to the proposed repository at Yucca Mountain, Nevada. The Plan describes how DOE’s Office of Civilian Radioactive Waste Management (OCRWM) intends to develop and implement a safe, secure and efficient transportation system and how stakeholder collaboration will contribute to

General Corrosion and Localized Corrosion of Waste Package Outer Barrier

The purpose and scope of this model report is to document models for general and localized corrosion of the waste package outer barrier (WPOB) to be used in evaluating long-term waste package performance in the total system performance assessment (TSPA). The waste package design for the license application is a double-wall waste package placed underneath a protective drip shield (SNL 2007 [DIRS 179394]; SNL 2007 [DIRS 179354]). The WPOB will be constructed of Alloy 22 (UNS N06022) (SNL 2007 [DIRS 179567], Section 4.1.1.6), a highly corrosion-resistant nickel-based alloy.

San Onofre PWR Data for Code Validation of MOX Fuel Depletion Analyses

The isotopic composition of mixed-oxide fuel (fabricated with both uranium and plutonium isotopes) discharged from reactors is of interest to the Fissile Material Disposition Program. The validation of depletion codes used to predict isotopic compositions of MOX fuel, similar to studies concerning uranium-only fueled reactors, thus, is very important. The EEI-Westinghouse Plutonium Recycle Demonstration Program was conducted to examine the use of MOX fuel in the San Onofre

slides - Dominion Work Related to High Burn-up Fuel Demonstration Project

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

Acceptance Priority Ranking & Annual Capacity Report

The Nuclear Waste Policy Act of 1982, as amended (the Act), assigns the Federal Government the responsibility for the disposal of spent nuclear fuel and high-level waste. Section 302a of the Act authorized the Secretary to enter into contracts with the owners and generators of commercial spent nuclear fuel and or high level waste. The Standard Contract for Disposal of Spent Nuclear Fuel and or High Level Radioactive Waste (Standard Contract) established the contractual mechanism for the Department's acceptance and disposal of spent nuclear fuel and high level waste.

slides - Fukushima Dai-ichi NPS Defueling Status

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

Assessment of Reactivity Margins and Loading Curves for PWR Burnup-Credit Cask Designs

This report presents studies to assess reactivity margins and loading curves for pressurized water reactor (PWR) burnup-credit criticality safety evaluations. The studies are based on a generic high-density 32- assembly cask and systematically vary individual calculational (depletion and criticality) assumptions to demonstrate the impact on the predicted effective neutron multiplication factor, keff, and burnup-credit loading curves. The purpose of this report is to provide a greater understanding of the importance of

Assessment of Fission Product Cross-Section Data for Burnup Credit Applications

Past efforts by the Department of Energy (DOE), the Electric Power Research Institute (EPRI), the Nuclear Regulatory Commission (NRC), and others have provided sufficient technical information to enable the NRC to issue regulatory guidance for implementation of pressurized-water reactor (PWR) burnup credit; however, consideration of only the reactivity change due to the major actinides is recommended in the guidance.

Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel

The purpose of this calculation report, Range of Applicability and Bias Determination for Postclosure Criticality of Commercial Spent Nuclear Fuel, is to validate the computational method used to perform postclosure criticality calculations. The validation process applies the criticality analysis methodology approach documented in Section 3.5 of the Disposal Criticality Analysis Methodology Topical Report.1 The application systems for this validation consist of waste packages containing transport, aging, and

Identification, Description, and Characterization of Existing and Alternative Nuclear Energy Systems

Fundamentally, a nuclear energy system uses nuclear fission to create heat, which is then available for generating electricity or other applications, including seawater desalination, heating, and production of other fuels. The nuclear energy system as currently deployed in the United States, Figure 1, consists of a number of integrated components, beginning with the natural resources required for nuclear fuel, followed by fissioning of the fuel in reactors connected to electricity generation facilities, and ending with the disposition of all wastes, including used nuclear fuel (UNF).

Probabilistic Criticality Consequence Evaluation (SCPB: N/A)

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department with the objective of providing a comprehensive, conservative estimate of the consequences of the criticality which could possibly occur as the result of commercial spent nuclear fuel emplaced in the underground repository at Yucca Mountain. The consequences of criticality are measured principally in terms of the resulting changes in radionuclide inventory as a function of the power level and duration of the criticality.

AN ANALYSIS OF INJURIES AT DEPARTMENT OF ENERGY WORK SITES

The Construction Industry Research and Policy Center (CIRPC) at the University of Tennessee was awarded a contract by the Center to Protect Workers’ Rights, under their grant program with the National Institute of Occupational Safety and Health (NIOSH), to analyze injuries of employees of the U. S. Department of Energy (DOE) and their contractors’ working at DOE work sites. The injury data analyzed were injuries recorded in DOE’s Computerized Accident Incident Reporting System (CAIRS).

slides - Management of Spent Fuel Pool Neutron Absorbing Material Degradation

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

Thermal Management Flexibility Analysis

The purpose of this report is to demonstrate that postclosure temperature limits can be met, and certain thermal characteristics of the postclosure thermal reference case can be preserved, with alternative thermal loading schemes. The analysis considers certain variations from the base case.waste stream, the predicted postclosure temperatures that develop within the rock mass due to these waste stream variations, and then compares these temperatures to postclosure temperature limits.

Volumes, Masses, and Surface Areas for Shippingport LWBR Spent Nuclear Fuel in a DOE SNF Canister

The purpose of this calculation is to estimate volumes, masses, and surface areas associated with (a) an empty Department of Energy (DOE) 18-inch diameter, 15-ft long spent nuclear fuel (SNF) canister, (b) an empty DOE 24-inch diameter, 15-ft long SNF canister, (c) Shippingport Light Water Breeder Reactor (LWBR) SNF, and (d) the internal basket structure for the 18-in. canister that has been designed specifically to accommodate Seed fuel from the Shippingport LWBR.

Preliminary Transportation, Aging and Disposal Canister System Performance Specification, Revision B

This document provides specifications for selected system components of the Transportation, Aging and Disposal (TAD) canister-based system. A list of system specified components and ancillary components are included in Section 1.2.

Proposed Alternative Strategy for the Department of Energy's Civilian Radioactive Waste Management Program: A Task Force Report

Over the decade since NWPA, the disposal program's strategy, based on its interpretation of the legislative mandate and regulatory requirements, has sought: • in a single large step and under a tight schedule, to achieve the first-of-a-kind licensing of a first-of-a-kind repository for isolating wastes from the human environment for many thousands of years. • in a single large step and as rapidly as possible, to build a full-scale repository and begin disposing of the bulk of the nation's inventory

Total System Model Version 6.0 Preprocessor Work Order Algorithm Validation Report

The purpose of this validation is to compare TSM simulation results using the manually calculated work orders (WO) for the transportation cask fleet to simulation results using an automated WO algorithm developed to estimate the cask fleet.

Civilian Nuclear Spent Fuel Temporary Storage Options

The Department of Energy (DOE) is studying a site at Yucca Mountain, Nevada, for a permanent underground repository for highly radioactive spent fuel from nuclear reactors, but delays have pushed back the facility’s opening date to 2010 at the earliest. In the meantime, spent fuel is accumulating at U.S. nuclear plant sites at the rate of about 2,000 metric tons per year. Major options for managing those growing quantities of nuclear spent fuel include continued storage at reactors, construction of a DOE interim storage site near

STARBUCS: A Prototypic SCALE Control Module for Automated Criticality Safety Analyses Using Burnup Credit

STARBUCS is a new prototypic analysis sequence for performing automated criticality safety analyses of spent fuel systems employing burnup credit. A depletion analysis calculation for each of the burnup-dependent regions of a spent fuel assembly, or other system containing spent fuel, is performed using the ORIGEN-ARP sequence of SCALE. The spent fuel compositions are then used to generate resonance self-shielded cross sections for each region of the problem, which are applied in a three-dimensional criticality safety calculation using the KENO V.a code.

Department of Energy Spent Fuel Shipping Campaigns: Comparisons of Transportation Plans and Lessons Learned

Presented at WM'03 Conference, Tucson, AZ, February 23-27, 2003