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Zirconium in the Nuclear Industry
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
NASA Technical Note
None
Waste Isolation Safeguards and Security System: Scoping study
The purpose of this study is to define the rationale and scope of the Waste Isolation System (WIS) safeguards system, to establish a set of proposed basic safeguards criteria, and to identify the areas requiring development of specific criteria and technology. The report also presents a proposed program schedule and provides an extensive bibliography of applicable reference safeguards documents. Volume one contains the following: glossary, system description; threat definition; safeguards regulations review - current and future; WIS safeguards criteria; assessment of criteria applicability and development requirements; and program plan. The report also presents a proposed program schedule and provides an extensive bibliography, in volumes two and three of applicable reference safeguards documents.
