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College students help develop waste measuring device at Hanford
Workers at Hanford recently used a new tool that uses radar to measure the depth of waste in underground tanks. (Photo: DOE)
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
Washington State engineering students worked with WRPS personnel to design what the DOE is calling “a safer and more efficient way” to measure the depth of the waste in Hanford’s large underground tanks.
Jean Boscary, Masanori Araki, Satoshi Suzuki, Koichiro Ezato, Masato Akiba
Fusion Science and Technology | Volume 35 | Number 3 | May 1999 | Pages 289-296
Technical Paper | doi.org/10.13182/FST99-A82
Articles are hosted by Taylor and Francis Online.
The purpose of the International Thermonuclear Experimental Reactor (ITER) divertor, which is located at the bottom of the vacuum vessel, is to exhaust impurities and their power from the plasma. Divertor plates function to withstand and to remove a steady-state surface heat flux of 5 MW/m2 and a transient peak heat flux up to 20 MW/m2 for 10 s on the side that faces the plasma. These demanding heat loads require active cooling by a pressurized subcooled flow of water as well as the development of a high-performance cooling channel to avoid burnout. Previous experiments showed that a screw tube, which is a tube whose inner surface is machined like a nut, is an efficient means of removing high heat fluxes. New experiments have been carried out with a B 0205 M10 type of screw copper tube. The average inner diameter, i.e., at the midheight of the fin, is 10 mm, and the outer diameter is 14 mm. Different pitches have been investigated: 1.5, 1.25, 1, and 0.75 mm. Incident critical heat fluxes (ICHFs) between 25 and 47 MW/m2 have been reached for local pressures ranging from 0.9 to 2.2 MPa, inlet temperatures from 17 to 33°C, and axial velocities from 3.6 to 14 m/s. ICHF increases as axial velocity increases and depends slightly on local pressure. Experimental results confirm the potentialities of the screw tube as a reliable geometry for fusion cooling tubes.