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NRC schedules webinars on Holtec’s proposed New Mexico storage site
The Nuclear Regulatory Commission has scheduled four webinars in late August and early September to present its draft environmental findings and receive comments on Holtec International’s proposed consolidated spent nuclear fuel storage facility in New Mexico. Webinars were previously held on June 23 and July 9.
As published in the August 13 Federal Register, the public comment webinars will be held on August 20 from 6–9 p.m., August 25 from 2–5 p.m., August 26 from 6–9 p.m., and September 2 from 11 a.m.–2 p.m. All times are Eastern. Information for the webinars is posted on the NRC’s Public Meetings webpage.
Vaclav Dostal, Pavel Hejzlar, Michael J. Driscoll
Nuclear Technology | Volume 154 | Number 3 | June 2006 | Pages 265-282
Technical Paper | Fission Reactors | dx.doi.org/10.13182/NT154-265
Articles are hosted by Taylor and Francis Online.
Supercritical carbon dioxide cycles are a promising power conversion option for future nuclear reactors operating with a reactor outlet temperature in the range of 550 to 650°C. The recompression cycle version operating with ~20-MPa turbine inlet pressure achieves similar cycle efficiencies as helium Brayton cycles operating at ~250°C higher turbine inlet temperature. The simplicity and high efficiency of the recompression cycle makes it a prime option from among the family of supercritical carbon dioxide cycles. The elimination of the need for intercooling due to the small required compressor work (because of the high density close to the critical point) makes the recompression cycle even simpler than helium Brayton cycles, which require intercooling to achieve attractive efficiencies. The high operating pressure reduces the size of the plant components significantly, making it a promising power cycle for low-cost modularized electricity-generating nuclear systems. However, the real gas behavior that improves the cycle efficiency presents a challenge for part-load operation. The traditional inventory control used for helium Brayton cycles may not be feasible. Bypass control is thus the prime option for part-load operation, making the cycle less efficient than during base-load operation. Since nuclear power plants are operated almost exclusively in base load, this drawback is not a disqualifying blemish.