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Division Spotlight
Fuel Cycle & Waste Management
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
C. B. Goodlett
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 259-267
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16316
Articles are hosted by Taylor and Francis Online.
Evaporation tests with synthetic alkaline wastes typical of intermediate-level waste streams from the processing of spent reactor fuel were made at the Savannah River Laboratory (SRL) with two small wiped-film evaporators [0.93 and 0.46 m2 (10 and 5 ft2) heat transfer area]. Each feed (six total) was processed separately within the operating range of each evaporator. Feed flows varied from 0.026 to 0.24 ℓ/min (0.1 to 0.9 gal/min) in increments of 0.026 to 0.013 ℓ/min (0.1 or 0.05 gal/min). Steam chest temperatures were maintained at 130, 150, 170, or 182 C. Rotor-tip speed was maintained at 10.7 m/s (35 ft/s). Concentrate and process condensate from the evaporator were sampled at each set of operating conditions. The concentrate sample was analyzed for density (at exit temperature), volume percent of solids at room temperature, weight percent of water, and sodium concentration. Each evaporator condensate sample was analyzed for sodium to calculate entrainment from the evaporator based on sodium carryover. All concentrates from waste feeds high in NaOH and NaAlO2 flowed freely in liquid form out of the evaporator. Concentrates from waste feeds containing Na2SO4 and Na2CO3 included appreciable amounts of precipitated solids at high boildowns. The tests showed that all of the feeds could be converted in one pass to a free-flowing slurry that solidifies upon cooling to ambient temperature. Wiped-film evaporators with ∼3.72 m2 (40 ft2) of heat transfer surface are being installed at SRL to determine mechanical operability and processing characteristics with simulated alkaline defense waste. Both visual and instrument control systems will be tested during operability tests of the prototype evaporators.