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Radiolytic Specie Generation from Internal Waste Package Criticality
Radiolytic Specie Generation from Internal Waste Package Criticality
EQ6 Calculation for Chemical Degradation of Pu-Ceramic Waste Packages: Effects of Updated Materials Composition and Rates
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.
slides - Operating Experience, Session I, Cask Cranes
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
slides - Transportation Infrastructure
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Transportation Readiness
slides - Transportation Readiness
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Vendor Perspective on Spent Fuel Pool Criticality Analysis
slides - Vendor Perspective on Spent Fuel Pool Criticality Analysis
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Second Waste Package Probabilistic Criticality Analysis: Generation and Evaluation of Internal Criticality Configurations
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
slides - Cumulative Impact of Industry and NRC Actions
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Slides - Retrievability, Cladding Integrity, and Safety Handling during Storage and Transportation
Slides - Retrievability, Cladding Integrity, and Safety Handling during Storage and Transportation
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Observations on Key Storage and Transport Technical Issues
slides - Observations on Key Storage and Transport Technical Issues
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
EQ6 calculations for Chemical Degradation of Navy Waste Packages
EQ6 calculations for Chemical Degradation of Navy Waste Packages
The Monitored Geologic Repository Waste Package Operations of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Navy (Refs. 1 and , 2). The Navy SNF has been considered for disposal at the potential Yucca Mountain site. For some waste packages, the containment may breach (Ref. 3), allowing the influx of water. Water in the waste package may moderate neutrons, increasing the likelihood of a criticality event within the waste package.
slides - Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste
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
slides - Transportation Planning Considerations: BRC Report Recommendations and Plans for Implementation
slides - Transportation Planning Considerations: BRC Report Recommendations and Plans for Implementation
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Transportation Readiness
slides - Transportation Readiness
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
slides - Advancing the Used Fuel Management Agenda
slides - Advancing the Used Fuel Management Agenda
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
Flexible Integrated Modular Nuclear Fuel Canister System
Flexible Integrated Modular Nuclear Fuel Canister System
Slides, Spark Presentation
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT SECOND NATIONAL REPORT
This report describes the actions taken in Argentina on the safety of spent fuel management
(SF) and on the safety of radioactive waste management, in order to provide evidence of the
fulfillment of its obligations under the Joint Convention. To facilitate the reading and a better
understanding of this report a summary of those parts of the 1st Report that were considered
necessary have been included.
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT
JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT THIRD NATIONAL REPORT
The present National Report describes the actions taken in Argentina on the safety of spent fuel
(SF) management and on the safety of radioactive waste (RW) management, in order to provide
evidence of the fulfilment of the obligations derived from the Joint Convention. To facilitate the
reading and a better understanding, it has been decided to include a summary of those parts of
the two prior National Reports that are considered necessary in order to comply with this
objective.
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
EQ6 Calculation for Chemical Degradation of Shippingport PWR (HEU Oxide) Spent Nuclear Fuel Waste Packages
The Monitored Geologic Repository (MGR) Waste Package Operations (WPO) of the Civilian Radioactive Waste Management System Management & Operating Contractor (CRWMS M&O) performed calculations to provide input for disposal of spent nuclear fuel (SNF) from the Shippingport Pressurized Water Reactor (PWR) (Ref. 1). The Shippingport PWR SNF has been considered for disposal at the proposed Yucca Mountain site.
Criticality Evaluation of Degraded Internal Configurations for the PWR AUCF WP Designs
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).
slides - Corrosion Monitoring of a Natural Convection Cooled Stored
slides - Corrosion Monitoring of a Natural Convection Cooled Stored
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013
General Corrosion and Localized Corrosion of Waste Package Outer Barrier
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.
slides - Dominion Work Related to High Burn-up Fuel Demonstration Project
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
slides - Fukushima Dai-ichi NPS Defueling Status
slides - Fukushima Dai-ichi NPS Defueling Status
Presented at the NEI Used Fuel Management Conference, St. Petersburg, FL, May 7-9, 2013