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Data Qualification Report: Mineralogy Data for Use on the Yucca Mountain Project

Data Qualification Report: Mineralogy Data for Use on the Yucca Mountain Project

Author(s)
T.L. Steinborn
Publication Date
This DQR uses the technical assessment methods according to Attachment 2 of AP-SIII.2Q, Rev. 0, ICN 3, to qualify DTN LADB831321AN98.002. The data addressed in this DQR have been cited in CRWMS M&O (2000b) to support the Site Recommendation in determining the suitability of Yucca Mountain as a repository for high level nuclear waste. CRWMS M&O (2000b) refers to mineral analyses that are unqualified.
yucca mountain repository license application data qualification tdr-nbs-hs-000005 minerals xrd mineral concentration

Supplement to the Disposal Criticality Analysis Methodology

Supplement to the Disposal Criticality Analysis Methodology

Author(s)
CRWMS
Publication Date
The Disposal Criticality Analysis Methodology Topical Report, YMP/TR-0004Q (DOE 1998b) described a risk-informed methodology for postclosure criticality analyses in the potential repository at Yucca Mountain, Nevada. Various models contained in the methodology were described and a process for validating these models was presented. The topical report also committed to following this process in validating the models used for License Application.
disposal neutronics analysis yucca mountain criticality analysis repository license application storage postclosure risk models b00000000-01717-5705-00137

Screening Analysis of Criticality Features, Events, and Processes for License Application

Screening Analysis of Criticality Features, Events, and Processes for License Application

Author(s)
Sandia National Laboratories
Publication Date
The purpose of this analysis report is to evaluate the features, events, and processes (FEPs) associated with criticality and document the screening decision for either inclusion or exclusion of criticality in the Total System Performance Assessment for License Application (TSPA-LA). The FEPs associated with criticality address scenarios that include initiators of sequences of events or processes that could lead to configurations that have potential for criticality in the repository.
criticality yucca mountain criticality analysis license application nrc storage regulations postclosure

Technical Evaluation Report on the Content of the U.S. Department of Energy's Yucca Mountain Repository License Application

Technical Evaluation Report on the Content of the U.S. Department of Energy's Yucca Mountain Repository License Application

Author(s)
Nuclear Regulatory Commission
Publication Date

This “Technical Evaluation Report on the Content of the U.S. Department of Energy’s Yucca Mountain License Application; Postclosure Volume: Repository Safety After Permanent Closure” (TER Postclosure Volume) presents information on the NRC staff’s review of DOE’s Safety Analysis Report (SAR), provided on June 3, 2008, as updated by DOE on February 19, 2009. The NRC staff also reviewed information DOE provided in response to NRC staff’s requests for additional information and other information that DOE provided related to the SAR.

yucca mountain license application repository safety nrc

MOX Spent Nuclear Fuel and LaBS Glass for TSPA-LA

MOX Spent Nuclear Fuel and LaBS Glass for TSPA-LA

Author(s)
Sandia National Laboratories
Publication Date

This analysis provides information necessary for total system performance assessment (TSPA) for the license application (LA) to include the excess U.S. Department of Energy (DOE) plutonium in the form of mixed oxide (MOX) spent nuclear fuel and lanthanide borosilicate (LaBS) glass. This information includes the additional radionuclide inventory due to MOX spent nuclear fuel and LaBS glass and the analysis that shows that the TSPA models for commercial spent nuclear fuel (CSNF) and high-level waste (HLW) degradation are appropriate for MOX spent nuclear fuel and LaBS glass, respectively.

high level waste yucca mountain commercial spent nuclear fuel license application radionuclides mox fuel spent fuel degradation

Report on Intact and Degraded Criticality for Selected Plutonium Waste Forms in a Geologic Repository

Report on Intact and Degraded Criticality for Selected Plutonium Waste Forms in a Geologic Repository

Author(s)
CRWMS
Publication Date

As part of the plutonium waste form development and down-select process, repository analyses have been conducted to evaluate the long-term performance of these forms for repository acceptance. Intact and degraded mode criticality analysis of the mixed oxide (MOX) spent fuel is presented in Volume I, while Volume II presents the evaluations of the waste form containing plutonium immobilized in a ceramic matrix.

criticality repository license application mox fuel immobilized plutonium ceramic waste form waste package degradation plutonium waste forms bba000000-01717-5705-00020

Initial Radionuclide Inventories

Initial Radionuclide Inventories

Author(s)
Bechtel SAIC Company, LLC
Publication Date

The purpose of this analysis is to provide an initial radionuclide inventory (in grams per waste package) and associated uncertainty distributions for use in the Total System Performance Assessment for the License Application (TSPA-LA) in support of the license application for the repository at Yucca Mountain, Nevada. This document is intended for use in postclosure analysis only.

yucca mountain commercial spent nuclear fuel license application radionuclides postclosure co-disposal waste package isotopic concentrations

Preclosure Criticality Safety Analysis

Preclosure Criticality Safety Analysis

Author(s)
Bechtel SAIC Company, LLC
Publication Date

The means to prevent and control criticality must be addressed as part of the Preclosure Safety Analysis (PCSA) required for compliance with 10 CFR Part 63 [DIRS 180319], where the preclosure period covers the time prior to permanent closure activities. This technical report presents the nuclear criticality safety evaluation that documents the achievement of this objective.

transportation yucca mountain criticality safety license application storage preclosure

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

slides - CFD Best Practice Guidelines (NUREG-2152), Thermal Modeling Issues, and Generic Communications Related to Vacuum Drying Operations

Author(s)
Solis, J.
Publication Date

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

slides nei used fuel management meeting cfd thermal modeling vacuum drying
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