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Radiolytic Specie Generation from Internal Waste Package Criticality

Radiolytic Specie Generation from Internal Waste Package Criticality

Author(s)
JOHN A. MCCLURE ,
GEORGETA RADULESCU
Publication Date
The effects of radiation on the corrosion of various metals and alloys, particularly with respect to in-reactor processes, has been discussed by a number of authors (Shoesmith and King 1998, p. 2). Shoesmith and King (1998) additionally discuss the effects of radiation on the proposed Monitored Geologic Repository (MGR) Waste Package (WP) materials. Radiation effects on the corrosion of metals and alloys include, among other things, radiolysis of the local gaseous and aqueous environment to produce both oxidizing and reducing radicals.
monitored geologic repository radiolysis corrosion internal criticality nitric acid production materials analysis engineered barrier system cal-ebs-nu-000017

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

General Corrosion and Localized Corrosion of Waste Package Outer Barrier

General Corrosion and Localized Corrosion of Waste Package Outer Barrier

Author(s)
Sandia National Laboratories
Publication Date

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.

yucca mountain storage total system performance assessment corrosion materials analysis radionuclide transport waste package outer barrier

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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