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Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package

Criticality Consequence Analysis Involving Intact PWR SNF in a Degraded 21 PWR Assembly Waste Package

Author(s)
John A. McClure ,
James R. Worsham, III
Publication Date
The purpose of this analysis is to evaluate the transient behavior and consequences of a worst case criticality event involving intact pressurized water reactor (PWR) spent nuclear fuel (SNF) in a degraded basket configuration inside a 21 PWR assembly waste package (WP). The objective of this analysis is to demonstrate that the consequences of a worst case criticality event involving intact PWR SNF are insignificant in their effect on the overall radioisotopic inventory in a WP.
storage isotopic concentrations 21 pwr waste package waste package degradation criticality consequence bba000000-01717-0200-00057

Westinghouse MOX SNF Isotopic Source

Westinghouse MOX SNF Isotopic Source

Author(s)
CRWMS
Publication Date

The purpose of this calculation is to develop an estimate of the isotopic content as a function of time for mixed oxide (MOX) spent nuclear fuel (SNF) assemblies in a Westinghouse pressurized water reactor (PWR). These data will be used as source data for criticality, thermal, and radiation shielding evaluations of waste package (WP) designs for MOX assemblies in the Monitored Geologic Repository (MGR).

thermal analyses criticality shielding pwr monitored geologic repository isotopic concentrations mox fuel bba000000-01717-0210-00007

Summary Report of SNF Isotopic Comparisons for the Disposal Criticality Analysis Methodology

Summary Report of SNF Isotopic Comparisons for the Disposal Criticality Analysis Methodology

Author(s)
CRWMS
Publication Date

The "Summary Report of SNF Isotopic Comparisons for the Disposal Criticality Analysis Methodology" contains a summary of the analyses that compare SNF measured isotopic concentrations (radiochemical assays) to calculated SNF isotop~c concentrations (SAS2H module ·orScale4.3). The results of these analyses are used to support the validation of the isotopic models for spent commercial light water reactor (LWR) fuel.

criticality scale commercial spent nuclear fuel repository sas2h lwr fuel disposal criticality analysis isotopic concentrations b00000000-01717-5705-00077

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

Author(s)
CRWMS
Publication Date

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.

criticality radionuclides isotopic concentrations waste package degradation corrosion internal criticality waste package development department mined geologic disposal system bba000000-01717-2200-00005

Probabilistic External Criticality Evaluation (SCPB: N/A)

Probabilistic External Criticality Evaluation (SCPB: N/A)

Author(s)
CRWMS
Publication Date

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development (WPD) department to provide a probabilistic evaluation of the potential for criticality of fissile material which has been transported from a geologic repository containing breached waste packages of commercial spent nuclear fuel (SNF). This analysis is part of a continuing investigation of the probability of criticality resulting from the emplacement of spent nuclear fuel in a geologic repository.

yucca mountain commercial spent nuclear fuel repository fissile material accumulation external criticality isotopic concentrations waste package development department mined geologic disposal system 880000000-01717-2200-00037 critical mass

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Dissolved Concentration Limits of Elements with Radioactive Isotopes

Author(s)
Sandia National Laboratories
Publication Date

The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments.

yucca mountain radionuclides dose calculation isotopic concentrations engineered barrier system geochemical analysis

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

Isotopic Generation and Confirmation of the BWR Appl. Model

Isotopic Generation and Confirmation of the BWR Appl. Model

Author(s)
Areva
Publication Date

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).

burnup credit bwr yucca mountain commercial spent nuclear fuel isotopic analysis criticality calculation isotopic concentrations

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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