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Probabilistic External Criticality Evaluation

Probabilistic External Criticality Evaluation

Author(s)
P. Gottlieb ,
J. R. Massari
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.
criticality safety mined geologic repository external criticality breached waste package

Disposal of Spent Nuclear Fuel and High-level Radioactive Waste

Disposal of Spent Nuclear Fuel and High-level Radioactive Waste

Author(s)
ENVIRON International Corporation
Publication Date

The characteristics of spent nuclear fuel and high-level waste are described, and options for permanent disposal that have been considered are described. These include:
•disposal in a mined geological formation,
•disposal in a multinational repository, perhaps on an unoccupied island,
•by in situ melting, perhaps in underground nuclear test cavities,
•sub-seabed disposal,
•disposal in deep boreholes,
•disposal by melting through ice sheets or permafrost,
•disposal by sending the wastes into space, and

disposal high level waste spent fuel reprocessing repository mined geologic repository deep borehole disposal used fuel

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

Report on Implementation of the Obligations under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management–Second Review Meeting of the Contracting Parties

SED Publication Type

Report on Implementation of the Obligations under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management–Second Review Meeting of the Contracting Parties

Author
General Secretariat, Council of The European Union
Publication Date

The European Atomic Energy Community (“Euratom”) is a regional organisation, as referred to in Article 39(4) of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. It became a party to the Convention on 2 January 2006. This report is submitted in compliance with Articles 30 and 32 of the Convention for the Second Review Meeting of the Contracting Parties, to be held in Vienna from 15 to 26 May 2006.

siting national report joint convention spent fuel management european union radioactive waste management

Technical Basis Report For Surface Characteristics, Preclosure Hydrology, And Erosion

SED Publication Type

Technical Basis Report For Surface Characteristics, Preclosure Hydrology, And Erosion

Author
Wesley E. Barnes ,
Stephan J. Brocoum
Publication Date

This study presents a synthesis of information and interpretations relevant to surficial processes at the Yucca Mountain Site. The report is part of the technical basis which will be used to evaluate the suitability of Yucca Mountain, Nevada, as a site for a mined geologic repository for the permanent disposal of high-level radioactive waste and spent nuclear fuel. It provides a description of the surface characteristics, preclosure hydrology, and erosion at the Yucca Mountain Site. This report will provide the technical basis to evaluate three technical guidelines from the U.S.

yucca mountain siting 10 cfr part 960 mined geologic repository
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