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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

Initial Waste Package Probabilistic Criticality Analysis: Multi-Purpose Canister With Disposal Container (TBV)

Initial Waste Package Probabilistic Criticality Analysis: Multi-Purpose Canister With Disposal Container (TBV)

Author(s)
CRWMS
Publication Date

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to provide an assessment of the present waste package design from a criticality risk standpoint. The specific objectives of this initial analysis are to:
1. Establish a process for determining the probability of waste package criticality as a function of time (in terms of a cumulative distribution function, probability distribution function, or expected number of criticalities in a specified time interval) for various waste package concepts;

multi-purpose canister (mpc) yucca mountain criticality analysis repository postclosure waste package design risk models waste package development department mined geologic disposal system b00000000-01717-2200-00080

Calculation of Upper Subcritical Limits for Nuclear Criticality in a Repository

Calculation of Upper Subcritical Limits for Nuclear Criticality in a Repository

Author(s)
CRWMS
Publication Date

The purpose of this document is to present the methodology to be used for development of the Subcritical Limit (SL) for post closure conditions for the Yucca Mountain repository. The SL is a value based on a set of benchmark criticality multiplier, keff> results that are outputs of the MCNP calculation method. This SL accounts for calculational biases and associated uncertainties resulting from the use of MCNP as the method of assessing kerr·

yucca mountain criticality analysis repository postclosure mcnp b00000000-01717-0210-00027 subcritical limit

Geochemistry Model Validation Report: Material Degradation and Release Model

Geochemistry Model Validation Report: Material Degradation and Release Model

Author(s)
Sandia National Laboratories
Publication Date

The purpose of the material degradation and release (MDR) model is to predict the fate of the waste package materials, specifically the retention or mobilization of the radionuclides and the neutron-absorbing material as a function of time after the breach of a waste package during the 10,000 years after repository closure. The output of this model is used directly to assess the potential for a criticality event inside the waste package due to the retention of the radionuclides combined with a loss of the neutron-absorbing material.

yucca mountain criticality analysis neutron absorbers postclosure materials analysis radionuclide transport neutron transport

The Potential of Using Commercial Duel Purpose Canisters for Direct Disposal

The Potential of Using Commercial Duel Purpose Canisters for Direct Disposal

Author(s)
Best, Ralph ,
McLeod, Barrie
Publication Date

This report evaluates the potential for directly disposing of licensed commercial Dual Purpose
Canisters (DPCs) inside waste package overpacks without reopening. The evaluation considers
the principal features of the DPC designs that have been licensed by the Nuclear Regulatory
Commission (NRC) as these relate to the current designs of waste packages and as they relate to
disposability in the repository. Where DPC features appear to compromise future disposability,
those changes that would improve prospective disposability are identified.

criticality tdr-crw-se-000030 rev 00 commercial dual purpose canisters commercial spent nuclear fuel postclosure

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

Thermal Management Flexibility Analysis

Thermal Management Flexibility Analysis

Author(s)
Sandia National Laboratories
Publication Date

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.

thermal analysis yucca mountain repository near field interactions postclosure total system performance assessment waste stream

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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