Published 2006 | Version v1
Miscellaneous

An optimized approach towards the treatment of high level liquid waste in the nuclear cycle

  • 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

Part of:
Book of abstracts. Fifteenth Pacific basin nuclear conference

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)

Optional Information