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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.
Isotopic Generation and Confirmation of the BWR Appl. Model
Isotopic Generation and Confirmation of the BWR Appl. Model
The objective of this calculation is to establish an isotopic database to represent commercial spent nuclear fuel (CSNF) from boiling water reactors (BWRs) in criticality analyses performed for the proposed Monitored Geologic Repository at Yucca Mountain, Nevada. Confirmation of the conservatism with respect to criticality in the isotopic concentration values represented by this isotopic database is performed as described in Section 3.5.3.1.2 of the Disposal Criticality Analysis Methodology Topical Report (Reference 7.1).
Waste Acceptance System Requirements Document, Revision 5, ICN 01
Waste Acceptance System Requirements Document, Revision 5, ICN 01
The purpose of this document is to establish waste acceptance technical requirements for the U.S. Department of Energy’s (DOE) Civilian Radioactive Waste Management System (CRWMS). These requirements and functions consist of two types: (a) internal CRWMS requirements derived from the Civilian Radioactive Waste Management System Requirements Document (CRD) (DOE 2007a) as illustrated in Figure 1, and (b) acceptance criteria imposed by the CRWMS on spent nuclear fuel (SNF) and high-level waste (HLW) delivered into the CRWMS.
One Step at a Time: The Staged Development of Geologic Repositories for High-Level Radioactive Waste - Summary
One Step at a Time: The Staged Development of Geologic Repositories for High-Level Radioactive Waste - Summary
A new report from the National Academies proposes a management approach called “adaptive staging” as a promising means to develop geologic repositories for high-level waste such as the proposed repository at Yucca Mountain, Nevada. Adaptive staging is a learn-as-you-go process that enables project managers to continuously reevaluate and adjust the program in response to new knowledge and stakeholder input.
Radioactive Waste Repository Licensing, Synopsis of a Symposium, Executive Summary
Radioactive Waste Repository Licensing, Synopsis of a Symposium, Executive Summary
This book recounts the issues raised and the viewpoints aired at a recent symposium on
repository licensing. It summarizes the problems surrounding the setting of an
Environmental Protection Agency standard for the release of radionuclides and the
regulatory problems inherent in meeting such a standard. Symposium participants came
from a variety of federal agencies and advisory groups, state governments, public interest
groups, engineering firms, national laboratories, and foreign and international
organizations.
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
Direct Radiation Dose Consequence Calculation for Category 1 and 2 Event Sequences
Performance objectives for the geologic repository operations area through permanent closure in 10 CFR 63.111 identify compliance with regulatory dose limits for workers and members of the public as a design objective. The purpose of this design calculation is to determine direct radiation dose consequences for Category 1 and 2 event sequences. It does not include worker dose assessment for recovery operations following Category 1 event sequences.
Disposal Subcommittee Report to the Full Commission DRAFT
Disposal Subcommittee Report to the Full Commission DRAFT
The Disposal Subcommittee of the Blue Ribbon Commission on America’s Nuclear Future has
commenced to address a set of issues, all of which bear directly on the central question: “How can the
United States go about establishing one or more disposal sites for high-level nuclear wastes in a manner
and within a timeframe that is technically, socially, economically, and politically acceptable?”
To answer this question and to develop specific recommendations and options for consideration by the
Radiation Effects of Isotopic Uncertainty for Burnup Credit Validation
Radiation Effects of Isotopic Uncertainty for Burnup Credit Validation
The objective of this calculation is to provide the uncertainty term for fission product and minor actinides which contributes to the determination of the critical limit for burnup credit calculations. The scope of this calculation covers PWR and BWR spent nuclear fuel. This activity supports the Criticality Department's validation of burnup credit. The intended use of these results is in future Criticality Department calculations and analyses.
DSNF and Other Waste Form Degradation Abstraction
DSNF and Other Waste Form Degradation Abstraction
Several hundred distinct types of DOE-owned spent nuclear fuel (DSNF) may potentially be disposed in the Yucca Mountain repository. These fuel types represent many more types than can be viably individually examined for their effect on the Total System Performance Assessment for the License Application (TSPA-LA). Additionally, for most of these fuel types, there is no known direct experimental test data for the degradation and dissolution of the waste form in repository groundwaters.
Factors Affecting Public and Political Acceptance for the Implementation of Geological Disposal
Factors Affecting Public and Political Acceptance for the Implementation of Geological Disposal
The main objective of this report is to identify conditions which affect public concern (either
increase or decrease) and political acceptance for developing and implementing programmes
for geologic disposal of long-lived radioactive waste. It also looks how citizens and relevant
actors can be associated in the decision making process in such a way that their input is
enriching the outcome towards a more socially robust and sustainable solution. Finally, it
aims at learning from the interaction how to optimise risk management addressing needs and
1999 Design Basis Waste Input Report for Commercial Spent Nuclear Fuel
1999 Design Basis Waste Input Report for Commercial Spent Nuclear Fuel
The purpose of this document is to provide waste quantity and sequencing information that serves as the design basis for commercial spent nuclear fuel (CSNF) arriving at the repository, and the information on the transportation systems that will be used to deliver this fuel. It is intended as input for waste package and repository design analyses needed to ensure that facilities are flexible enough to be capable of receiving, unloading, handling, and emplacing the amounts and types of CSNF expected for receipt under realistic bounding conditions.
Attachment 2 - Annual Cost Profile (in Millions of 2007$), reply to Letter to Mr. Tim Frazier
Attachment 2 - Annual Cost Profile (in Millions of 2007$), reply to Letter to Mr. Tim Frazier
The table is based on historical costs through 2006, which are shaded, and projected costs in the 2008 TSLCC. To convert to 2010$, multiply by 1.0586. The 2008 TSLCC assumes a single repository system capable of accepting and disposing of SNF and HLW equivalent to 122,100 Metric Tons of Heavy Metal (MTHM). This estimate includes all defense wastes currently destined for disposal at Yucca Mountain and projected discharges of SNF from commercial utilities, including the 47 nuclear power reactors that had received license extensions from the NRC as of January 2007.
Engineered Barrier System: Physical and Chemical Environment
Engineered Barrier System: Physical and Chemical Environment
The purpose of this model report is to describe the evolution of the physical and chemical environmental conditions within the waste emplacement drifts of the repository, including the drip shield and waste package surfaces. This report documents the development of a new process-level model, the near-field chemistry (NFC) model, and develops two abstraction models.
Configuration Generator Model
Configuration Generator Model
The Disposal Criticality Analysis Methodology Topical Report prescribes an approach to the methodology for performing postclosure criticality analyses within the monitored geologic repository at Yucca Mountain, Nevada. An essential component of the methodology is the Configuration Generator Model for In-Package Criticality that provides a tool to evaluate the probabilities of degraded configurations achieving a critical state.