Scientific basis for nuclear waste management XVI

Conference · Thu Dec 30 23:00:00 EST 1993

OSTI ID:25013

Interrante, C G ^[1]; Pabalan, R T ^[2]

---

1. ed.; Nuclear Regulatory Commission, Washington, DC (United States)
2. ed.; Southwest Research Inst., San Antonio, TX (United States)

One most significant aspect of this particular symposium is the focus on the scientific basis for management of nuclear waste. Engineering principles and practices are important, but this symposium focuses on the science. The extension and application of engineering ``know how`` to waste management problems sometimes requires a degree of understanding not normally needed to solve other engineering problems. In materials science, for example, scientific understandings important to long-term behavior may be obtained from (1) characterizations and analyses of the structure and properties of materials, (2) the recognition of advancements needed to ensure performance, and (3) improvements in methods of fabrication and processing. In addition to the materials science topics addressed here (on waste forms, engineered barrier systems, and the near-field environment), the symposium addressed various far-field topics. The proceedings are divided into the following sections: spent fuel; glass and crystalline waste forms; glass performance--mechanisms and models; cementitious materials; container alteration; microbiologically influenced corrosion; near-field interactions; natural analogues; long-term prediction for engineered barriers; performance assessment of engineered barrier systems; radionuclide chemistry and transport; and performance assessment of geological systems. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

• Sponsoring Organization: USDOE, Washington, DC (United States); Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 25013
• Report Number(s): CONF-921101--Vol.294; ISBN 1-55899-189-1
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
AMERICIUM
AQUIFERS
BENTONITE
BIOLOGICAL FOULING
CARBON STEELS
CEMENTS
CESIUM
CONTAINERS
CONTAINMENT SYSTEMS
CORROSION
GROUND WATER
HIGH-LEVEL RADIOACTIVE WASTES
LEACHING
LEADING ABSTRACT
MATERIALS TESTING
MATHEMATICAL MODELS
MEETINGS
NEPTUNIUM
OXIDATION
PERFORMANCE TESTING
PLUTONIUM
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE PROCESSING
RADIONUCLIDE MIGRATION
SOLIDIFICATION
SPENT FUELS
STAINLESS STEELS
TECHNETIUM
THERMODYNAMICS
TRITIUM
TUFF
UNDERGROUND DISPOSAL
VITRIFICATION
WASTE FORMS
WIPP
YUCCA MOUNTAIN
Yucca Mountain Project