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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

External Criticality Risk of Immobilized Plutonium Waste Form in a Geologic Repository

External Criticality Risk of Immobilized Plutonium Waste Form in a Geologic Repository

Author(s)
Abdelhalim A. Alsaed ,
John A. McClure
Publication Date

This technical report provides an updated summary of the waste package (WP) external criticalityrelated
risk of the plutonium disposition ceramic waste form, which is being developed and
evaluated by the Office of Fissile Materials Disposition of the U.S. Department of Energy (DOE).
The ceramic waste form consists of Pu immobilized in ceramic disks, which would be embedded
in High-Level Waste (HLW) glass in the HLW glass disposal canisters, known as the "can-incanister"

high level waste spent fuel yucca mountain criticality analysis plutonium mined geologic repository high level waste glass used fuel

Disposal Criticality Analysis for Aluminum-based Fuel in a Codisposal Waste Package - ORR and MIT SNF - Phase II

Disposal Criticality Analysis for Aluminum-based Fuel in a Codisposal Waste Package - ORR and MIT SNF - Phase II

Author(s)
J. Wesley Davis ,
J. R. Massari ,
Chi Kang,
Publication Date

The objective of this analysis is to characterize the criticality safety aspects of a degraded Department of Energy spent nuclear fuel (DOE-SNF) canister containing Massachusetts Institute of Technology (MIT) or Oak Ridge Research (ORR) fuel in the Five-Pack Defense High-Level Waste (DHLW) waste package to demonstrate concept viability related to use in the Mined Geologic Disposal System (MGDS) environment for the postclosure time frame.

spent fuel mined geologic repository mcnp waste package design mit orr used fuel
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