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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

Long-term Safety for KBS-3 Repositories at Forsmark and Laxemar—a First Evaluation: Main Report of the SR-Can project

Long-term Safety for KBS-3 Repositories at Forsmark and Laxemar—a First Evaluation: Main Report of the SR-Can project

Author(s)
Swedish Nuclear Fuel and Waste Management Co
Publication Date

This document is the main report from the safety assessment project SR-Can. The SR-Can project is a preparatory stage for the SR-Site assessment, the report that will be used in support of SKB’s application for a final repository. The purposes of the safety assessment SR-Can are the following:
1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant.

disposal spent fuel repository sweden used fuel
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