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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.
Chuanxin Zhu, Yuan Chen, Yunfeng Mou, Pu Zheng, Tie He, Xinhua Wang, Li An, Haiping Guo
Nuclear Science and Engineering | Volume 169 | Number 2 | October 2011 | Pages 188-197
Technical Paper | doi.org/10.13182/NSE10-35
Articles are hosted by Taylor and Francis Online.
Measurements of (n, 2n) reaction cross sections to produce 84Rb, 86Rb, 88Y, 139Ce, 141Ce, 168Tm, 174m+gLu, 180mTa, 184m+gRe, 196n+gAu, and 237U were carried out in the range of 13.4 to 14.8 MeV. The samples were irradiated at various positions on the surface of a two-ring orientation instrument with a 20-cm radius centered at the deuterium-tritium neutron source. The 27Al(n,)24Na reaction was used to monitor the neutron fluence in the target samples. The neutron energies of different directions were determined using the ratio of 89Zr to 92mNb specific activities induced in Zr and Nb foils by (n, 2n) reactions. The (n, 2n) products were measured using a calibrated Ge detector. Experimental uncertainty was within ±4%. The results are presented and compared with the results of references and ENDF/B-VII.0 evaluations. Cross sections of 85Rb(n, 2n)84Rb, 140Ce(n, 2n)139Ce, and 89Y(n, 2n)88Y were in good agreement with those of ENDF/B-VII.0 evaluations; however, disagreements were observed for 175Lu(n, 2n)174Lu and 142Ce(n, 2n)141Ce between the present data and the ENDF/B-VII.0 evaluation file. The present data showed improvement in accuracy in comparison with previously reported data; therefore, the results should be offered for evaluations of neutron (n, 2n) cross sections.