An optimized approach towards the treatment of high level liquid waste in the nuclear cycle
Creators
- 1. The Battelle Energy Alliance at the Idaho National Laboratory, Idaho Falls, Idaho, USA, (United States)
- 2. Idaho State University, Idaho Falls, Idaho, USA, (United States)
Description
Full text: One key long-standing issue that must be overcome to realize the successful growth of nuclear power is an economical, politically acceptable, stakeholder-compatible, and technically feasible resolution pertaining to the safe treatment and disposal of high-level liquid radioactive waste (HLLW). In addition to spent nuclear reactor fuel, HLLW poses a unique challenge in regard to environmental and security concerns, since future scenarios for a next generation of domestic and commercialized nuclear fuel cycle infrastructures must include reprocessing - the primary source of HLLW-to ensure the cost effectiveness of nuclear power as well as mitigate any threats as related to proliferation. Past attempts to immobilize HLLW - generated by both the weapons complex and the commercial power sector-have been plagued by an inability to convince the public and some technical peer reviewers that any proposed geological disposal sites (e.g., Yucca Mountain) can accommodate and contain the HLLW for a period of geological time equivalent to ten fold the radiological half-life of the longest lived of the actinides remaining after reprocessing. The paper explores combined equipment and chemical processing approaches for advancing and economizing the immobilization of high level liquid waste to ensure its long term durability, its decoupling from the unknown behavior of the repository over long geological time periods, and its economical formulation as required for the nuclear fuel cycle of the future. One approach involves the investigation of crystalline based waste forms as opposed to the glass/amorphous based waste forms, and how recent developments in crystalline forms show promise in sequestering the long lived actinides for over tens of millions of years. Another approach -compatible with the first- involves the use of an alternative melter technology-the Cold Crucible Induction Melter (CCIM)- to overcome the engineering material problems of Joule Heated Meters (JHM) as well as it's inability to be flexible to a wide variety of HLLW compositions and waste formulations
Additional details
Publishing Information
- Publisher
- Australian Nuclear Association
- Imprint Place
- Sydney (Australia)
- Imprint Title
- Book of abstracts 15"t"h Pacific basin nuclear conference
- Imprint Pagination
- 331 p.
- Journal Page Range
- p. 167
Conference
- Title
- 15. Pacific basin nuclear conference
- Dates
- 15-20 Oct 2006
- Place
- Sydney (Australia)
INIS
- Country of Publication
- Australia
- Country of Input or Organization
- Australia
- INIS RN
- 39036762
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACTINIDES; DEVELOPED COUNTRIES; ENVIRONMENTAL EFFECTS; ENVIRONMENTAL PROTECTION; FISSION PRODUCTS; IDAHO; LIQUID WASTES; NORTH AMERICA; NUCLEAR FUELS; NUCLEAR POWER; RADIOACTIVE EFFLUENTS; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTES; SECURITY; SPENT FUELS
- Descriptors DEC
- DEVELOPED COUNTRIES; ELEMENTS; ENERGY SOURCES; FUELS; ISOTOPES; MANAGEMENT; MATERIALS; METALS; NORTH AMERICA; NUCLEAR FUELS; POWER; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; REACTOR MATERIALS; USA; WASTE DISPOSAL; WASTE MANAGEMENT; WASTES