EQ6 Calculation for Chemical Degradation of Enrico Fermi Codisposal Waste Packages: Effects of Updated Design and Rates

The Monitored Geologic Repository (MGR) Waste Package Project of the BSC Management and Operating Contractor for the Department of Energy's Office of Civilian Radioactive Waste Management performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Enrico Fermi Reactor owned by the DOE (Ref. 9). The Fermi SNF has been considered for disposal at the proposed Yucca Mountain site.

Prediction of the Isotopic Composition of UO2 Fuel from a BWR: Analysis of the DU1 Sample from the Dodewaard Reactor

As part of a larger program to study mixed-oxide fuel subject to high burnup, some UO2 samples were exposed and analyzed. This report discusses results from the analysis of a UO sample that was burned in a boiling-water reactor (BWR) to approximately 57 GWd/t. The sample

Managing the Nation's Commercial High-Level Radioactive Waste

This report presents the findings and conclusions of OTA's analysis of Federal policy for the management of commercial high-level radioactive waste. It represents a major update and expansion of the analysis presented to Congress in our summary report, Managing Commercial High-Level Radioactive Waste, published in April of 1982 during the debate leading to passage of the Nuclear Waste Policy Act of 1982 (NWPA). This new report is intended to contribute to the implementation of NWPA, and in particular to

Analysis of Dust Deliquescence for FEP Screening

The purpose of this report is to evaluate the potential for penetration of the Alloy 22 (UNS N06022) waste package outer barrier by localized corrosion due to the deliquescence of soluble constituents in dust present on waste package surfaces. The results support a recommendation to exclude deliquescence-induced localized corrosion (pitting or crevice corrosion) of the outer barrier from the total system performance assessment for the license application (TSPA-LA).

Nuclear Waste Facility Siting and Local Opposition

On the historic evidence, but also for the distinctive qualities of the challenge, nuclear waste siting conflicts are assuredly among the most refractory in the large variety of NIMBY (Not In My Back Yard) facility siting disputes. Since the president brought the Yucca Mountain process to a halt in 2010 (or, more accurately, issued its death certificate), the search for a permanent waste fuel repository is at the starting line again.

Internationalization of the Nuclear Fuel Cycle: Goals, Strategies, and Challenges

Following the proposals for nuclear fuel assurance of International Atomic Energy Agency (IAEA) Director General Mohamed ElBaradei, 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

Options for Developing Public and Stakeholder Engagement for the Storage and Management of Spent Nuclear Fuel (SNF) and High Level Waste (HLW) in the United States

This report puts forth a number of options and recommendations for how to engage stakeholders and other members of the public in the storage and management of spent nuclear fuel and high level waste in the United States. The options are generated from a scientific review of existing publications proposing criteria for assessing past efforts to engage publics and stakeholders in decision-making about risky technologies. A set of nine principles are derived for evaluating cases of public and stakeholder engagement with

slides - Generic Issue Management--An Idea Taking Flight

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

U.S. Regulatory Recommendations for Actinide-Only Burnup Credit in Transport and Storage Casks

In July 1999, the U.S. Nuclear Regulatory Commission (NRC) Spent Fuel Project Office (SFPO) issued Interim Staff Guidance 8 Revision 1 (ISG8R1) to provide recommendations for the use of burnup credit in storage and transport of pressurized-water reactor (PWR) spent fuel. Subsequent to the issuance of ISG8R1, the NRC Office of Regulatory Research (RES) has directed an effort to investigate the technical basis for extending the criteria and recommendations of ISG8R1 to allow

Management of Commercially Generated Radioactive Waste

In the course of producing electrical power in light water.reactors (LWRs), the uranium fuel accumulates fission products until the fission process is no longer efficient for power production. At that point the fuel is removed from the reactor and stored in water basins to allow radioactivity to partially decay before further disposition. This fuel is referred to as "spent fuel." Although spent fuel as At is discharged from a reactor is intensely radioactive, it has been stored safely in moderate quantities for decades. Spent fuel could

slides - DOE Nuclear Fuel Storage and Transportation (NFST) Planning Project: System Analysis and Integration Activities

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

Preclosure Consequence Analyses

The purpose of this calculation is to demonstrate that the preclosure performance objectives specified in 10 CFR 63.111(a) and 10 CFR 63.111(b) (Reference 2.2.1) have been met for the proposed design and operations in the geologic repository operations area (GROA) during normal operations and Category 1 event sequences, and following Category 2 event sequences. Category 1 event sequences are those natural and human-induced event sequences that are expected to occur one or more times before permanent closure of the repository.

slides - EPRI High Burnup Used Fuel Confirmatory Demonstration Project [The "High Burnup Demo"]

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

slides - Minimum Critical Volume

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

Cladding Degradation Summary for LA

The purpose of this analysis report is to develop the summary cladding degradation abstraction that will be used in the Total System Performance Assessment for the License Application (TSPA-LA). Most civilian commercial nuclear fuel is encased in Zircaloy cladding. The analysis addressed in this report is intended to describe the postulated condition of commercial Zircaloy-clad fuel as a function of postclosure time after it is placed in the repository.

Reactor Record Uncertainty Determination

The objective of this calculation is to evaluate commercial spent nuclear fuel (CSNF) bumup uncertainty based on pressurized water reactor (PWR) and boiling water reactor (BWR) records kept by each utility. The bumup uncertainties will be used to adjust either the waste package loading curves or the bumup values of assemblies shipped to the repository. This engineering calculation supports the burnup credit methodology in Reference 1 and is performed in accordance with the AREVAIFANP procedures in References 2 and 3.

slides - Nuclear Generation Event Response: Strengthening Safety After Fukushima

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

Study of the Effect of Integral Burnable Absorbers for PWR Burnup Credit

The Interim Staff Guidance on burnup credit issued by the U.S. Nuclear Regulatory Commission's Spent Fuel Project Office recommends restricting the use of burnup credit to assemblies that have not used burnable absorbers. This restriction eliminates a large portion of the currently discharged spent fuel assemblies from cask loading, and thus severely limits the practical usefulness of burnup credit.

3rd WP Probabilistic Criticality Analysis: Methodology for Basket Degradation with Application to Commercial SNF

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to describe the latest version of the probabilistic criticality analysis methodology and its application to the entire commercial waste stream of commercial pressurized water reactor (PWR) spent nuclear fuel (SNF) expected to be emplaced in the repository. The purpose of this particular application is to evaluate the 21 assembly PWR absorber plate waste package (WP) with respect to degraded mode criticality performance.

Mortality of Older Construction and Craft Workers Employed at Department of Energy (DOE) Nuclear Sites

Background The U.S. Department of Energy (DOE) established medical screening programs at the Hanford Nuclear Reservation, Oak Ridge Reservation, the Savannah River Site, and the Amchitka site starting in 1996.Workers participating in these programs have been followed to determine their vital status and mortality experience through December 31, 2004. Methods A cohort of 8,976 former construction workers from Hanford, Savannah River, Oak Ridge, and Amchitka was followed using the National Death Index through December

slides - ISFSI Security Rulemaking Update

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

Foreign Research Reactor West Coast Shipment Spent Nuclear Fuel Transportation - Institutional Program External Lessons Learned

The purpose of the Foreign Research Reactor (FRR) Spent Nuclear Fuel (SNF) Shipments Institutional Program was to meet the goals and commitments of the Implementation Strategy Plan for the FRR SNF Shipments. This program provided a systematic approach to planning, implementing, evaluating, and validating preparedness for the first west coast shipment of SNF from Asian countries to the Idaho National Engineering and Environmental Laboratory (INEEL).

Memo to Timothy Collins from Laurence Kopp - Guidance on the Regulatory Requirements for Criticality Analysis of Fuel Storage at Light-Water Reactor Power Plants

Guidance concerning regulatory requirements for criticality analysis of new and spent fuel storage at light-water reactor power plants used by the Reactor Systems Branch.

CRC Depletion Calculations for Three Mile Island Unit 1

The purpose of this calculation is to document the Three Mile Island Unit 1 pressurized water reactor (PWR) fuel depletion calculations performed as part of the commercial reactor critical (CRC) evaluation program. The CRC evaluations support the development and validation of the neutronics models used for criticality analyses involving commercial spent nuclear fuel in a geologic repository.

Canister Handling Facility Criticality Safety Calculations

This design calculation revises and updates the previous criticality evaluation for the canister handling, transfer and staging operations to be performed in the Canister Handling Facility (CHF) documented in BSC (Bechtel SAIC Company) 2004 (DIRS 167614).