Radiological risk evaluation for risk-based design criteria of the multiple canister overpack packaging
Author(s) -
Westinghouse Hanford Green J.R.
Publication year - 1996
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/657357
Subject(s) - engineering , interfacing , reliability engineering , process (computing) , criticality , containment (computer programming) , component (thermodynamics) , electromagnetic shielding , computer science , operating system , physics , electrical engineering , nuclear physics , computer hardware , thermodynamics , programming language
The Multiple Canister Overpack (MCO) cask will be used in the transportation of irradiated nuclear fuel from the K Basins to a Canister Storage Building. This report presents the radiological risk evaluation, which is used in the development of the design criteria for the MCO cask. The radiological risk evaluation ensures compliance with the onsite transportation safety program
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