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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
Kyoung-Ho Kang, Hyun-Sik Park, Seok Cho, Nam-Hyun Choi, In-Cheol Chu, Byong-Jo Yun, Kyung-Doo Kim, Yeon-Sik Kim, Won-Pil Baek, Ki-Yong Choi
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 382-394
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT12-A13482
Articles are hosted by Taylor and Francis Online.
A postulated steam generator tube rupture (SGTR) event of the APR1400 (Advanced Power Reactor 1400 MWe) was experimentally investigated with the thermal-hydraulic integral effect test facility ATLAS (Advanced Thermal-Hydraulic Test Loop for Accident Simulation). The SGTR accident is one of the design-basis accidents having a significant impact on safety from the viewpoint of radiological release. To simulate a SGTR accident of the APR1400, the SGTR-HL-04 and the SGTR-HL-05 tests were performed by simulating double-ended ruptures of a single U-tube and five U-tubes at the hot side of the ATLAS steam generator. Following the reactor trip induced by a high steam generator level signal, the primary-system pressure decreased and the secondary-system pressure increased until the main steam safety valves were opened to reduce the secondary-system pressure. A mild change of the water level in the core was observed, which was attributed to the small break sizes of the present tests compared with conventional loss-of-coolant-accident tests. No excursion in the cladding temperature was observed in either test. The break area affected the timing of the major events observed in the tests. Lessened heat transfer to the secondary side caused by earlier actuation of the safety injection pumps had more influence on the secondary pressure of the affected steam generator than the break flow. The break flow was discharged as single-phase water in both tests.