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Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Annual Conference
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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.
P. M. Prajapati, H. Naik, S. Mukherjee, S. V. Suryanarayana, B. S. Shivashankar, R. Crasta, V. K. Mulik, K. C. Jagadeesan, S. V. Thakre, S. Ganesan, A. Goswami
Nuclear Science and Engineering | Volume 176 | Number 1 | January 2014 | Pages 106-113
Technical Paper | doi.org/10.13182/NSE12-78
Articles are hosted by Taylor and Francis Online.
The yields of various fission products in the neutron-induced fission of 232Th have been determined a using recoil catcher and off-line gamma-ray spectrometric technique with flux-averaged energies of 5.42, 7.75, and 10.09 MeV. The neutrons were generated using the 7Li(p,n) reaction at the BARC-TIFR [Bhabha Atomic Research Centre–Tata Institute of Fundamental Research] Pelletron facility, Mumbai, India. The fission product–yield data in the 10.09-MeV neutron-induced fission of 232Th are determined for the first time. The yields of the different fission products in the neutron-induced fission of 232Th with flux-averaged energies of 5.42 and 7.75 MeV from the present work have been compared with similar data of comparable neutron energy from the literature and are found to be in good agreement. The effect of nuclear structure on fission product yields as a function of neutron energy has been examined.