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Fusion Science and Technology
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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
Anisia Bornea, Marius Zamfirache, Liviu Stefan, Ioan Stefanescu
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1411-1414
Detritiation and Isotope Separation | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12695
Articles are hosted by Taylor and Francis Online.
The National Research and Development Institute for Cryogenics and Isotopic Technologies (ICIT Rm. Valcea) was established in 1970 as a research focused Industrial Pilot Plant with the main goal of developing a heavy water production technology.Within ICIT there is an experimental pilot plant for tritium and deuterium separation, which has as main purpose the development of tritium separation technique from heavy water used as moderator in CANDU-like nuclear reactors as those existent at CNE Cernavoda.The CNE Cernavoda detritiation installation (CTRF) was designed primarily to reduce the level of tritium from the reactor moderator 1 of the nuclear power plant, from 54 Ci/kg - an estimated value to be achieved in 15 years of continuous operation, up to a threshold of maximum 0.54 Ci/kg.Under a contractual agreement ICIT Rm.Valcea and AECL are to jointly produce both a pre-feasibility and feasibility study for the project. The pre-feasibility study completed in August 2006, provided the rationale for choosing the Liquid Phase Catalytic Exchange-Cryogenic Distillation process for the Cernavoda TRF.After reaching the planned threshold in the water of moderator 1, the CTRF can alternatively provide the reduction in heavy water activity from the moderator of reactor 1 and 2 respectively.