The Waste Isolation Pilot Plant


Book Description

This volume discusses the readiness of the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) facility near Carlsbad, New Mexico, to serve as a geological repository for transuranic radioactive waste. WIPP is located in a Permian-age bedded salt deposit 658 meters below the surface. The committee has long reviewed DOE's readiness efforts, now aimed at demonstrating compliance with U.S. Environmental Protection Agency regulations. Site characterization studies and performance assessment modeling are among the topics considered in this volume.







NCRP Report


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Proceedings of PSAM--II


Book Description







Scientific Basis for Nuclear Waste Management XIX: Volume 412


Book Description

Safe and effective management of nuclear waste provides a broad range of challenges for materials science. Waste processing, waste form and engineered barrier properties, interactions between engineered and geological systems, radiation effects, chemistry and transport of waste species, and long-term predictions of repository performance are just some of the scientific problems facing modern society. This book, the nineteenth in a very successful series from MRS, offers an international and interdisciplinary perspective on the issues, and features developments in both fundamental and applied areas. Topics include: excess plutonium dispositioning; spent nuclear fuel; glass waste forms; ceramic and crystalline waste forms; cement waste forms; waste processing; waste container materials; speciation and sorption; bentonite barriers; flow and transport; repository site characterization; natural analogs and performance assessment.




Government Reports Annual Index


Book Description

Sections 1-2. Keyword Index.--Section 3. Personal author index.--Section 4. Corporate author index.-- Section 5. Contract/grant number index, NTIS order/report number index 1-E.--Section 6. NTIS order/report number index F-Z.




Actinide Speciation in High Ionic Strength Media


Book Description

The management and disposal of radioactive wastes are key international issues requiring a sound, fundamental scientific basis to insure public and environmental protection. Large quantities of existing nuclear waste must be treated to encapsulate the radioactivity in a form suitable for disposal. The treatment of this waste, due to its extreme diversity, presents tremendous engineering and scientific challenges. Geologic isolation of transuranic waste is the approach currently proposed by all nuclear countries for its final disposal. To be successful in this endeavor, it is necessary to understand the behavior of plutonium and the other actinides in relevant environmental media. Conceptual models for stored high level waste and waste repository systems present many sCientific difficulties due to their complexity and non-ideality. For example, much of the high level nuclear waste in the US is stored as alkaline concentrated electrolyte materials, where the chemistry of the actinides under such conditions is not well understood. This lack of understanding limits the successful separation and treatment of these wastes. Also, countries such as the US and Germany plan to dispose of actinide bearing wastes in geologic salt deposits. In this case, understanding the speciation and transport properties of actinides in brines is critical for confidence in repository performance and risk assessment activities. Many deep groundwaters underlying existing contaminated sites are also high in ionic strength. Until recently, the scientific basis for describing actinide chemistry in such systems was extremely limited.