1993
DOI: 10.13182/nt93-a34846
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Radiological Safety Experience in the Fabrication of Alloy Plate Fuels Bearing233U/Pu

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“…7 In the meantime, a 1993 article from the Bhabba Atomic Research Center in Bombay reported a 6.7 person-rem summed dose incurred by workers fabricating a research-reactor core containing 0.6 kg "clean" U-233 containing 3 ppm U-232. 8 Interest in U-233 as a Reactor Fuel One reason for interest in U-233 as a reactor fuel is the superior conversion ratios Cp that can be achieved with it in slow-neutron reactors. 9 It will be seen from Table 1 that about 0.2 more neutrons are produced on average per "thermal" (20 °C or 0.025 eV) neutron absorbed on U-233 than for absorption in Pu-239.…”
Section: U-232 Radiation Hazardmentioning
confidence: 99%
“…7 In the meantime, a 1993 article from the Bhabba Atomic Research Center in Bombay reported a 6.7 person-rem summed dose incurred by workers fabricating a research-reactor core containing 0.6 kg "clean" U-233 containing 3 ppm U-232. 8 Interest in U-233 as a Reactor Fuel One reason for interest in U-233 as a reactor fuel is the superior conversion ratios Cp that can be achieved with it in slow-neutron reactors. 9 It will be seen from Table 1 that about 0.2 more neutrons are produced on average per "thermal" (20 °C or 0.025 eV) neutron absorbed on U-233 than for absorption in Pu-239.…”
Section: U-232 Radiation Hazardmentioning
confidence: 99%